ML050870138

Reactor Coolant System Reduced Inventory Requirements & Nozzle Dam Operational Regs, Unit 1

ML050870138
Person / Time
Site:	Point Beach
Issue date:	05/18/2004
From:	Groehler R - No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
2004-0471, FOIA/PA-2004-0282
Download: ML050870138 (40)

Text

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RVIEN'V AN!) APPROVAL.

.Ntw.- Ro/i io , X' 1.2.3. Tentpor, (a f u inent.s. Page I of 9.

I - INITIATION Doc Number OP 4F Current Rev I Unit 111PH Temp Chaine No. 2004-0471 D IReactor Coolant System Reduced Inventory Requirements and No'zle Dam Operational Requirements Documenti Title Unit I E xisting Effective Temporary Changes nWa Description _See PBF-0026c tIf recesun. continue deicription of chxnes. on Pit F-OU26C and atlazh

[ Initiate PI3F-0026h and include with the change.

Other documents required to be effective concurrently with the temporary change: n/a Changes pre-screened according to NP 5.1.8? El NO Z YES (rtniJz d.:micniation ac ing ia Nil 5A SI Screening completed according to NP 5. 1.8? 2 NA El YES (Avach copy)

Safetv Evaluation Required? N NO M ITES 0' e!s. mj.bc pocisd ,t Fnal ruvicils and ppfvlsha! hc tbuncd befre implontne Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions.

(If any answers are 1ITS. a revkiion ma% he processed or final rev iess and approsaki sha!l hc obtained before implementing)

Will the proposed change: Y rs NO

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

2. Cause an increase in magnitude, significance or impact such that a rev. should be processed? 7E

3. 1)elete or modify a prerequisite, initial condition, precaution. limitation or other steps that could have safety si-nificance or affect the procedure's margin of safety? ElE

4. Delete QC hold points, Independent Verification or Concurrent Check steps %% ithout 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? O- E

6. Require a change to the .procedure Purpose or change the procedure classification? O El Initiated By (print'sign) Ross Groehler tZA I/  ; 1 _ Date 05/1 4/2004 11If-IN\ITIAL A"BO(VAL, Group Supervisor 1__1_j AL Date 51 1 ____

(Cannot be the Initiat0r) Thi3 chat2e k efrcme and complet1c. can be performed as u~ritlen. and doe-s not ad' Lrsei% aDlfect personnel or nuclear ,a 1civ. (i Plant operaiin. conditions.

Senior Reactor Operator (print'si-n) - . / Date o S_ /C WCawinnt be the Initiator or Group Supervi,wr) Ihis change dnes not adersch alkc:t I'Mit opdlting conditinns (Safcty RP.ir-d prwcdarcs onth)

Ill - PROCEDURE OWNER REV!IEW 3 Perr'ianelnt El One-timc Use El Expiration Date, Event or Condition:

rraining reviewv recommended per Ni' 1.2.3? El NO Z YES (il Yes, RFT Number per NP 1.2.3 f:T 132'- L _

n, lold change until procedure completed (final reuieis and approtal still required within 14 days of initial approval)

QC reviev%required according toNP 1.2.3/NP 8.4.1? O NA Ol YES (If yes, QC Signature)

EI QR'POR(: Re'ie' CNO'1 Required (Admin.'NNSRun!%) E QR Resiers Required POR(' Revicv Riequired itcfercnt P I 6tS Procedure Owner (prin'sign) P.r / r _Date Sj I his Change and sorprning rcLuiremnents currectly~cornplcted and procSsed.

IV - FINAL REVIEW AND APPROVAL (NI ist he riiripletcd isithin 14 d as of initialI a ppro%SI) (1 I' ItliiQ audApproiNi AtithoritIv hallI be indepn dentI fromt ea ch other)

ORm__ ____ Iate J;PORC M'eetimn, a~-An-T4o IrdLIS50 5972.48 applicahility assessed, an',/cess5 ~. cri'ning!evaluamions pertformed. dac Min Zion made as to N~hether ad.litionil Cr,1"-dFiJPlin~tr% re% ies required, and if rcqul AI '~I'Md.

Arnnro~ ;l Authority torin~'iegn)t - IA; 11 -, .//,1 --  ! - Date ' - ,) e L(

I'ot ~itg evesIpin~iN? R3TEVISION INFORN1ATlON FOR PERMNANF.NT CIIAN(;kES Jod~cate, teprachneWs incorporo.'te cxaztl as airr-.ntland no ('t1cr ch.,nce maide to docurment.

[Ilkorporaie-.d nto, Revision Number ____Efl1ectivc Dale' ______

0 1,III :-W 12N: ,: ,;.; v,. .3;<

Ds-. I. i"', 1 4 ."t. III, r 0.

P~oin1t B.-chl Nuclear Plant D)OCIUJMENT RI:vl EW AND APPROVAL CONTINUATION l'J.e ~Lof 4 Doc 'Number O 4F Revision I Unit j111)

Title Reactor Coolant SNystem Reduced Inventory Requirements :mnd NozzC l)am Operational Requirements U'iit I Temporary Change Number 20(14-0477 I Description of Changes:

Step Changce/Reason 1OC Added Table Of Contents.

Removed reference to Ol 163, Si, RI IR and CS PUMP Runs. and Venting Si Pump Casings. Feedback from Operator JITT (Just in Time Training) expressed concern that ifS pumips were vented bh! anothier procedure such as Ol- I2S, Si system Fill and Vent Unit I, they could not sign off Step. Prescreened to 3.10 Criteria I Editorial Change.

Added "During Reduced inventorv" Clarification as to when PML applies. Prescreened to Criteria I 3.11 Editorial Chance.

Added Equipment identifiers associated with equipment description. Prescreened to Criteria I Editorial 3.14 Chanme.

Added step to ensure this procedure was intended to be used for this refueling outage. This action is bein- taken to address concerns associated wvith nozzle dam guidance beine contained in a procedure for reduced inventory. This guidance had to be placed in this OP 41: because PBNP does not have a nozzle 4.1.1 dam procedure. CA1P0565741. Ilrescreened to Criteria I Editorial Change.

Added " Ensure high alarms for each thermocouple set at 135 and 195 decrees Fahrenheitn Prescreened to 4.1.5 criteria 6.

Modified the initial condition as follo%%s deleted "rc'.iew the" and added ".are met tor enterinm reduced 4.1.6 inventorv". Clarification of what is expected by Figure 1. Prescreened to Criteria I [Editorial Change.

Added initial condition for one narrow ranme RVLIS instrument available. This was an e.xistin-4.1. II precaution and limitation that %wasworded as an initial condition. Prescreened as Criteria I Editorial.

deleted step associated " ith initial conditions tor installing the last nozzle dam. CAIP 056605 Feedback from Operator JITT (Just in Time Trainine) expressed concern over how to sign off step if'just in reduced inventory and not installing nozzle dams. Step deletion will allow procedure to be completed without 4.2. 4.2.1 confusion associated over how to sicn off. Prescreened to Criteria 6 Xlaintenance activitv.

5.1.2.a.. b.. c. Added Equipment identifiers to equipment description. Prescreened to Criteria I Editorial chance.

Removed reference to TS 3.4.7. Nlode 5 RCS Loops Filled. CAI 056605 Feedback from Operator JITT (Just in Tinte Training) wondered how this tech spec applied if current guidance in OP 4D part I state that tubes will be burped if intry into Reduced inventory is desired. Prescreened to criteria 4. OP 4D) Part 5.1.3 I Added unit desienator and equipment descriptors for SW-144 and SWV- 176. CAP' 056605 Feedback from Operator JITT (Just in Time Training) requested that this be added to procedure. Prescreen to criteria I S.l.X Editorial change.

Other Comments

• Nowk Icrding oil' Stcp NumnhLra, inflLt requirLd l;r mullipic occurrenccs ;' idenical inl;.m:n::iohn or mhm no1 cIU iett t.nre%imcers tIF-OO'N; Ro jkionj,,(h4 1 ovIrcenxic t Nr I 1 3. Nr, 2 3'

Point B~each Nucle.ar Plant D)OCL2'ME.NT REV'l W AND AP1TI(VALI CO)NTINUATION P~aiu ". of ~

Doc Numbcr 01P 4F Revision I Unit RI'l I

Title Rleoictor Coolant SS stem Rcduced Inventor%Requlirenients and Nozzle Daim Operational Requirements Ullit I Temporarv Chlane Number 2004-(11 Deleted "Nlay hase other duties assiumned by shift maaii-eer" This concern *\as addressed because Dedicated operator usage was not applicable and Shift nianagemient wanted discretion to use the control operator for other duties (not to interfere with monlitoring RCS inventory and RIIR operations). Without this guidance there %%illbe questions associated sith using assigned CO to perform any duties beyond 5.1 .9.a monitorin_ the above mentioned tasks. Prescreened to Criteria I Editorial Challae.

Added "OR a member ofSthe Fire B3ricade" to statement which described the responsibilities of the 5.1.9.c Auxiliary Operator in regards to Oil 4F. Prescreen to criteria I editorial chance Note prior to Added informational note associated with nozzle dam installation. note is to let operator know that 5.1.12 procedure may be continued. Prescreen to criteria I Editorial chanCe.

Added step to initiate new attachment D. Shifily reduced insentory checks. Step is to ensure requirements 5.1.12 exist %hiluie in reduced inventorv. I'rescreen to criteria 6.

Reworded high level step. Step w'ill now control nozzle dami installation requirements. No longer will these requirements be initiated before the last nozzle dami is installed. The' will be initiated before noze71 dams are installed. This will ensure hot leg vent path exists before any nozzle dam is installed. Previous to this se allowed the vent paths to be the S.(i prinmiry main ays and controlled the logic to installing the nozzle dams. This change will prevent this logic path from beini used and will require a vent be available 2 prior to installingL, nozzle dams. Prescreen to criteria 6.

5.2.3.a, 5.2.3.bh S.3. 1.c bullets, 5.3;2.b: bullets Added equipment name to valves. Prescreened to criteria I editorial.

Reworded high level step to ensure section is more clearly defiled. Also reformatted step to flow with

5. 3. 5. 3. I Reactor vessel head on. editorial in nature no chanue to intent. Prescreeneed to criteria I Added step to initiate Attachment EAShiftls Nozzle Wall Checks. These checks are formatted after like

3.6 checks in RP-IC refueling procedure. Prescreened to Criteria 6 Added P&L from 01-1 I associated with nozzle dams air leakace. This nowe has been added as an informational note to ensure operations is aware of this potential. The potential for air leakage into Cold Note prior to Ieg could be such that up to 305 gallons could be needed for reflood. Prescreen to criteria I Editorial step 5.4 chance.

5.4 Ressorded high level step. Prescreened to criteria 1 editorial 5.4.1, 5.4.1 .a. Reformatted step to allow protected signage to be removed prior to !getting to exact level tor removal. this 5.4. .b will give a heads up to remove the siens since there are a lot of them. Prescreen to criteria 6.

5.5.3 bullets Added Unit designators to SW valves. Prescreened to criteria I Editorial.

Other Comments N;

N RcctLrdin, or Skp Nir.hwrs, i nt rcquir~d I~r multipte o rrcnxc ot iJ~zaicait int~rmition or tv!en no ki tiIi to res IC crv IrttYo00e.;

Rcsiioni 6 41S ( l Rtcrec:lc Nl I 3. N i I 3I'

I'oin; Reach Nucleair Plan D)OCUMENT RFV'IEWV AND) APPROVAL CONTINUATIo.N Pace 4 of Doc Number Oil -F Revision I Unit 1111 Tite lreactor Coolant Swstem lRduced Inventory lRquircenits and Nozzle l)am Operational Requirements Unit I Temporary Chan!e Number 20(4-0471

1. Added informational note stating that fiure I is not appropriate flor nozzle dams requirements.

CAP 05f6605 Feedback from Operator JITT (Just in Time Training) requested that this be addressed in procedure. Nozzle dam usage requires a hot leg, vent path and thesc requirements are delineated in P&L 3.19 Nozzle Darns. Prescreened to Criteria I Editorial Chariec

2. Added Figure I title to 2 nd page of figure I. Prescreened to Criteria I Editorial Change

3. Revised tigure to include entry point and arrows for movement through diagram.

4. Added more information on containment closure requirements to alloux entry into reduced Figure I inventorv. P'rcscreen to criteria 6.

Attachment A, Attachment 13 Revised note. 'Note wvas aligned with exact verbiage of NP 10.3.6. Prcscreen to criteria 4.

Created nev attachment D. Shiftlv Reduced Inventorv Checks. This attachment incorporates required Attachment D checks to maintain required conditions necessary for reduced inventory. Prescreen to criteria 6.

Created new attachment E, Shiftlv Nozzle Dani Checks. This attachment incorporates required checks to maintain required conditions necessary for nozzle darn installation with head on or head off. Prescreen to Attachment E criteria 6.

5.2.8 Chanued title of step. This changed because step 5.3 wordingh change. prescreened to criteria I Editorial 4-4.

. Note. Recording of Stcp Numinhen,' ik ,,t re.utuiret fir multiple olccurfcix st ide!ntical iifornialtioin or %dheinol holefilti.1 tk res ie4rs PB~lF!0026C Rc% ision 6 041181SQ Kcrcenciv NP' i 1.3. Nl 1 2 3

P'oint Btach Nuclear P'laint TEMP.NII'OIRAIRY CI IAN(;EI, A-F:FECI'I) M\IANLUAL LOCATION Paue 5__ of -

Procedure Number O' 4F Revision Unit Reactor Coolant SNstem Reduccd Inventory Requirements anied Nozzle Dani Operational Requircmients Title Unit I Temporary Change Number 2004-047 I - MIM IEI)IATELY'AF1'.R INITIAL APIZROVAL ON I'BF-0026c (Non-Intent chlanacs)

(aftur Final Approal it ciiange of intcnt in%okcdj I Date Performed This procedure change has been processed as follows: (Manual'Location)

El Copy included in work package for field implementation. (WO No. )

El Sign offs for completed work and QC stamps included'transferred in work-package or procedure for field implementation. (WO No. )

1 Copy filed in Control Room temp chance binder (Operations only).

S Original change package provided to 4.414 ctvc -> to obtain Procedure Owner Review (e.g., O%%ner review may be coordinated by In-Group OA 11. Procedure Writer, Procedure Supervisor, etc.).

El _

_l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

El _____ _

El ____, _

Performed By (print and sign)

KGLiAvt z4 . *. G

- ' _0eL Date 1-f r-e f 11 - PROCEDURE OWNER REVIEW ON P13F-0026c (may be performed by OA 11. Procedure Writer. etc.)

D)ate Performed This procedure chance has been processedi as follovs: (Manual./Location)

Copy of permanent changes to Operations procedures forwarded to Emergency I'lanning and _ l Simulator Trainine within the nem normal working day after initial approval.

Co(p sent to Document Control Dlistribution l.ead for Master File.

(Not required for one-time use change)

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

l (Copy filed in Group one-tinme use file.

F 3 Original Temp Change provided to _5 to obtain I'inal Approvals (c.--. final approval may be coordinated hN In-Group OA IL. Procedure Writer, Procedure Supervisor, 5 -'Y etc.)

Performed B3N -jjr~.

(print and sign Dame .:

HIF -W-6t h}

IZLk I..j k .- ,,  ! . i A-r.,rvi-v 1' I Ž.,

Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENING RElV1EN' Page j of '

Brief Activitv Title TCN 2004-0471 to Oil 4F, Reactor Coolant System Reduced Inventory Requirements and or

Description:

Nozzle Darn Operational Requirements Unit I This form is required to be completed and attached to the applicable activity change forms (i.e., PBF-0026ac, etc.) to document use of Pre-scrcenino Criterion 3 through 6 for 10 CFR 50.59 / 72.48 review of proposed changes (see 'N' 5.1.8, 10 CFR 50.59/72.48 Applicability, Screening and Evaluation (New Rule) Section 4.6 and Attachment A.)

Pre-screening Criterion 3 - Activity Covered by Existing 10 CFR 50.59 / 72.4S Screening or Evaluation Criterion 3 is Z Not Applicable to the proposed activity.

Identify the screenin- or evaluation numnber(s) (SE for old 50.59/72.48 rule evaluations, EVAL for new rule evaluations):

SCR I SE / EVAL ;(s): SPEED 9 (NP 9.3.3. Rev. 3 or later ONLY):

If applicable, briefly summarize the paris of the proposed activity that are covered by Pre-screening Criterion 3.

VERIFY THAT ALLI OF THE FOLLOWING ARE TRUE FOR CHANGES THAT ARE PRE-SCREENED Verified TO CRITERION 3:

The current licensings basis has been searched. The licensing basis APPLICABLE to the activity AND to the atfected systems. structures or components has NOT changed since the screenings or evaluation was completed.l The screening or evaluation has NOT been cancelled OR superceded by another screening or evaluation (i.e., E either via a revision to the original screening or evaluation, or completion of a new screening or evaluation).

The referenced screening or evaluation was completed AFTER December 1, 2001, OR the proposed activity does not involve a Method of Evaluation (see NMIC 50.59 Resource Manual Section 3.10 for definition) AND does not involve a Desien Basis Limit for a Fission Product Barrier (see NP 5.1.8, Attachment E for list).

Pre-screening Criterion 4 - Activity Covered by Existing Approved and Valid Plant Procedure Criterion 4 is El Not Applicable to the proposed activity.

Identify the applicable plant procedure.

Procedure number, revision and title: OP 4D Part I rev 63, Part I Draining the Reactor Coolant System., NP 10.3.6, rev.1 I Outaae safetv review and assessment.

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

OP 41r Part I Removed TS 3.4.7 from 5.1.3. To enter OPI4F S'G Tubes must be drained, therefore loops filled TS can not be applicable.

NP 10.3.6 erbia,,e on Attachment A and Ed%%erechanced to match verbiage on NP 10.3.6 associated with work on protected equipment.

Pre-screening Criterion 5- N'RC has Reviewed andi Approved the Activity.

Criterion S is Z Not Applicable to the proposed activity.

Identify the NRC Safety Evaluation Report Number andor Date.

I NRC SER(s) a, or Date(s):

PBFl-IiIIb Reviiion2 (0/22,'01 Re"Vrtni C. 1x'I' j.l X

Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENIN(; IWVIEPo'f Y If applicable, briefly summarize tile parts of the proposed activity that are covered Iy Pre-screenine 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.)

Criterion 6 is E Not Applicable to the proposed activity.

If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screenin: Criterion 6.

Installing nozzle dams are a maintenance function associated with S/G inspections. Added stCps to ensure Thermocouple alarms arc properly set. This wvill ensure alarm function to support reduced inventory operation.

Revised step associated with nozzle dam installation. Previous step wvanted requirements prior to installing tile last hlot leg nozzlc dam. With this change we are going to institutc tiese requirements prior to installing any nozzle dams.

Step associated with removal of protected equipment signage was moved ahead to allow signage to be removed earlier.

Figure I w'as enhanced to better describe flow patlhs to allow reduced inventory conditions. This enhancement included better descriptions of containment closure and a start box.

Created two new attachments to allow for better monitoring of requirements need for reduced inventory and for Nozzle Dam installation. These are formatted after RP-IC, refueling checks.

VERIFY TI IAT NONE OF TIHE FOLI.QNOING CHANGES ARE PRE-SCREENED TO CRITERION 6: V'crified No changes to structure, system or component design, performance, acceptance criteria, types of materials, torque values outside of vendor recommended values, etc. (NOTE: Use Criterion 3 for SPEEDs.)

No temporary alterations to support maintenance or modification installation vill be in place longer than 90 days. (If there is any doubt whether the temporary alteration will be removed in 90 days. perform a screening.)

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

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 wvithin the scope of Prescreening Criteria 3, 4, 5, or 6 of NP 5.1.8.

F.ITIIER prcparer O1R reviewer shall be 50.59!72.48 screening or evaluation qualified.

Performed B3 Ross Groehlcr I L c - 05/16/04 Name (Print) Sig-nature Revieciied By RvC, %i W V - - Date /iL1 0 Name (Print) Si-nature Rcslic.n 2 01/2210-1 Rchertv Nl'S I S

OP 4F REACTOR COOLANT SYSTEM REDUCED INVENTORY REQUIREMENTS AND NOZZLE DAM OPERATIONAL REQUIREMENTS UNIT 1 I)OCUMENT TYPE: Technical CLASSI Fl CATI ON: Safety Related REV71SION: I

FFECTIVE I)ATE

May 10, 2004 REVIEWVER: Plant Operation's Review Committee APPROVAL AUTHORITY: Dcpartment, Manager PROCED)URE ONVINE:R (title): Group Head OWNER1l1 GROUP: Operations Verified Current Copy:

Signature Date Time l ist pages used for Partial Performance Controlling Work Document Niumbers Completed Procedure Review:

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

POINT BEACH NUCLEAR PLANT OP41:

OPERATING PROCEI)URES SAFETY RELATEI)

Revision I REACTOR COOLANT SYSTES M REDUCED May 10, 2004 INVENTORY REQUIREMENTS AND NOZZLE DAM OPERATIONAL REQUIREIMENTS UNIT I TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ............................ 3 2.0 PREREQUISITES ................................... 3 3.0 PRECAUTIONS AND LIMITATIONS ................................... 3 4.0 INITIAL CONDITIONS .................................... 8 Initial Conditions for Entering Reduced Inventory .................................... 8 5.0 PROCEDURE.................................... 10 O Entering Reduced Inventory Conditions ................................... 10 Nozzle Dam Installation Requirements ................................... 17 Nozzle Dam Requirements While Installed ................................... Is NJ Nozzle Dam Removal ................................... 20 2 Termination Of Reduced Inventory Condition ................................... 21

6.0 REFERENCES

................................... 23 7.0 BASES ................................... 23 Figure 1, Reactor Coolant System Reduced Inventory Requirements .23 Attachment A, Protected Equipment For Unit I In Reduced Inventory . .27 Attachment B, Protected Equipment While Steam Generator Nozzle Dams Are Installed .. 29 Attachment C, Additional Support Personnel For Reduced Inventory Operations . .30 Attachment D, Shiftly Reduced inventory Checks .. 3 Attachment E, Shiftly Nozzle Dam Checks .. 33 Page 2 of 33) o(ONTINUOUS USE

POINT IIEACI-I NULLAR l'LANT1' OP'41F Olil-RATl(i PROCED)URES SAFE'TY RELATE.D Revision 1 REACTOR COOLANT SYSTEMI REDUCED MNIay 10. 2004 INVTENTORY REQUIREMENTS AND NOZZLE D)AN OPE1RATIONAL REQUIREMENTS UNIT 1 1.0 PURPOSEI 1.1 Define the reduced inventor! condition of the Reactor Coolant System.

1.2 Define the various analyzed Reactor Coolant conditions possibl& ashen at reduced inventorsN.

1.3 Define the methods of makeup to the reactor core available when in each of the analyzed conditions of reduced inventory operation.

1.4 Provide directions for meeting various system requirements prior to entering a reduced inventory condition.

1.5 Provide plant operational requirements for installing and removing nozzle dams as specified in Generic Letter 88-17. (1-4) 1.6 Provide plant operational requirements when nozzle dams are installed.

2.0 PREREQUISITES ,

None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Reduced inventory condition of the Reactor Coolant System is defined as Reactor Vessel level less than 55% as indicated on I LI-447/447A. This level is approximately 3 feet below the Reactor Vessel flange.

3.2 Do NOT pump water from the CVCS Holdup Tanks until RCS draining has been completed.

3.3 The drain rate from the RCS shall be controlled to assure orderly level reduction. IF any doubts about level indication exist, THE N draining shall be stopped.

3.4 Since the inventor) of reactor coolant is less than normal while in reduced inventory, boiling can occur in a very short amount of time (minutes). RHR flow for core heat removal shall be maintained at all times except when switching trains (wNhich should be avoided if possible) as allowed hb r.s. 3.4.8 RCS Loops-MODE-5, Loops not filled.

3.5 IF a loss of all AC powver occurs wvlhile performing this procedure.

ThEN the actions of SEP-3.0. Loss of All AC Poxer to a Shutdown Ugnit, shall be performed.

Page 3 of 3)3 Page 3 oCONTINUOUS USE

POi;INT BEACH NUCLE-AR PLANT OPl 41:

OPERATING PROCEDURES SAFFTY RifLA'YE)

Revision I

REACTOR COOLANTSYSTEMN REI)UCED Mma' 10. 2004 INVETNTORY REQUIREMENTS AND NOZZLE DA I)A OPERATIONAL REQUIRENMENTS UNIT I 3.6 IF a malfunction of the RI IR system occurs while performing this procedure.

TIhl iEN the actions of SEP-I, I)egraded RI JR System Capability, shall be performed.

3.7 RCS level indication mav NOT be accurate in the event of a loss of decav heat removal while a large veant opening in the Pressurizer exists and the Steam Generator nozzle damns arc installed.

3.S IF the manwavx covers on the Steam Generators (primary side) are removed ANI) the nozzle dams are No rinstalled, lEIiEN extreme care shall be taken to prevent primary coolant from spilling out of the Steam Generator man\\avs.

3.9 Other plant activities that may impact this evolILtion shall be suspended for the duration of reduced inventory operation.

3.1 0 The Si pumps shall be vented prior to operatioiper-I-163> Sl~---R4I4I-and---S-P-tj)

Rlins-an eti, nSlI'kpasinss if:

3. 10.1 The R\VST level has dropped below six (6) percent, OR 3.10.2 The SI System has undergone maintenance such that a portion of the suction piping to the pumnp(s) has been drained.

3.1,1 During Reduced Inventor, operations shall NOT be permitted that wvill cause perturbations to the RCS and/or to systems that are necessary lo maintain the RCS in a stable and controlled condition. Items to be considered include (but are not limited to):

3.11.1 Potential leakage past primary system isolation valves 3.11 ].2 Removal of RCS or RHR monitoring equipment from service 3.11 .3 Availability of Component Cooling Water and Service Water 3.11 .4 Reliability of Safeguard punmps' poxver supplies 3.11 .5 Larme increase in Auxiliary Feedwater to the Steam Generators 3.12 The unit shall be in a stable condition (no RCS draining in progress) prior to turnover to the next shift.

3.13 When in reduced inventory, there shall be at least 2 available or operable means of adding inventory to the reactor coolant system in addition to the RIIR system.n One system shall be a SI pump available for upper plenum injection. The other shall be a Charging pump with suction from the RWST, OR the Refueling Water Circ pump with a suction from the R\V'ST, OR one Spent Fuel Pool punmp.

. Page 4 of 3333 CONTINUOUS UTSE

P`OINTBIEACI I NUCLEAR PL.ANT 01' 41' OPERA'ING PROC('IDURE'S SAFETY RELAT'D)

Revision I REACTOR COOLANT SYSTEM RED)UCEI) Mlay 10. 2004 INVENTORY REQUIREMENTS AND NOZZLE DANI OPERATIONAL REQUIRENIENTS UNIT I 3.14 Wohen in reduced inventory at least one Narrow Range RVLIS instrument shall remain available. (1I-496 or 11-497, R-1 RIV Narrow Range Level Indicator) 3.15 RCS Loops-Mode 5, Loops Not Filled 3.15.1 1'S 3.4.8: Two Residual Hcat Removal (RI-IR) loops shall be OPERABLE and one RHR loop shall be in operation.

3.15.2 All R14R pumps may be NOT in operation for less than or equal to 15 minutes when switching from one loop to another provided:

a. The Core outlet temperature is maintained greater than I 00 F below saturation temperature.

b. No operations are permitted that would cause reduction of the RCS boron concentration.

c. No draining operations to further reduce the RCS water volume are permitted.

3.1 5.3 One R1HR loop may be inoperable for less than or equal to two hours for surveillance testing provided that the other RHR loop is OPERABLE and in, operation.

I ,

Pauc 5 of 33 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT OP 41 OPERATING PROCEI)URES SAFETY RELATED Revision I REACTOR COOLANT SYSTEM REDUCED 1%'lay 10. 2004 INVENTORY RE-QUIREM4ENTS AND NOZZLE DAM OPERLA\TIONAL REQUIREMENTS UNIT I 3.16 Low Temperature Overpressure Protection (LTOP) System Applicability: Mode 4 when any RCS Cold Leg temperature is less than or equal to the LTOP enabling temperature (270'F) specified in the PTLR, Mode 5, Mode 6 when the Reactor Vessel Hlead is on.

3.16.1 TS 3.4.12; An LTOP System shall be OPERABLE with:

a. A maximum of one Safety Injection (SI) pump capable of injecting into the RCS;

• The inoperable SI pump shall have its associated 4160 volt breaker racked out (Admin control),

OR

• Its discharge valve SHUT with operator power removed, its discharge cross-connect SHUT, AND the pump control switch in PULLOUT (Admin control)

b. Each Accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR (TRM 2.2, Figures 1 and 2), and

c. One of the following pressure relief capabilities:

l Two power operated relief valves with lift settings within the limits specified in the PTLR, or a The RCS depressurized and an RCS vent path wvith venting capability equivalent to or greatcr than a PORNV.

3.17 Shutdowni M9vargin (SDMI); Applicability: Modes 4 and 5 T S 3.1.1; TRM 2.1 (COIR); Shutdown Margin (SDM) shall be greater than or equal to 1% AKJK.

Page 6 of 131 CONTINUOUS USE

POINT 131 ACI I NUCLFAR PLANT 01) 41:

OP'ERATING PROC1)1'IRES SAFETYd LATIED Revision I RE7ACTOR COOLANT SYSTEM REDUCED 1Mta 10. 2004 INVENTORY REQUIRENMENTS AND NOZZLE DAM OPERATIONAL REQUIREMENTS UNIT I 3.18 Boron Dilution Alarm: Applicability: MIODE 5 3.18.1 TS 3.3.6; Boron Dilution Alarm shall be OPERAB3LE-.

• IF the Boron Dilution Alarm becomes inoperable in Mode 5.

THEN the unborated water source valve(s) must be closed Xwithin one hour. TS 3.3.6, Condition A. Required Action A.] .

NOTE: P&L 3.19 applies only -%hen nozzle darns are installed.

3.19 Nozzle Dams (B-4) 3.19.1 Cold leg nozzle darns shall be installed prior to installing the last hot leg nozzle dam.

3. 19.2 One hot leg nozzle dam shall be removed prior to anyi cold leg nozzle dam.

3.19.3 To prevent nozzle dam blowout, an adequate hot leg vent path must be established and maintained. Acceptable hot leg vent paths for nozzle dam installation are:

a. The Reactor Vessel head raised to greater than or equal to I inch above the Reactor Vessel flange is acceptable.

b. The Pressurizer manwvay opening is acceptable if the Reactor has been shut dow\n for greater than or equal to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

c. Both Pressurizer code safeties removed is acceptable if the Reactor has been shut down for greater than or equal to 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

NOTE: A SI pump control switch may be removed from PULLOUT and the discharge valve opened for approved testing (c.g., IT 760), provided the Reactor Vessel head is removed. A SI pump control switch may also be removed from PUJLLOUT and the discharge v,'lv e opened if directed by an approved Shutdown Emergencv Procedure (SEP).

3.19.4 To prevent nozzle dam blowout. BO3TH S1 pumps control swilches shall be in PULLOUT ANI) associated discharge valves (1 SI-866A and I SI-866B) SHUT.

Pane 7 of 33 CONJTINUOULS USE

POINTBEACI NUJCILEAR PLANT 01) 4F OPERATING PlROCEI)URES SAFETY RELATDI-Revision I RE ACTOR COOLANT SYSTE-M1 REDUCEI) May 10. 2004 IN'EN'TORY REQUIREIMIENTS ANO NOZZLE DAMI OPERATIONAL REQUIREMENTS UNIT I INITIALS 4.0 INITIAL CONDITIONS NOTE: Section 4.1 does not apply if the reactor is defucled.

4.1 Initial Conditions for Enterine Reduced Inventorv (Section 5.1) 41 4.1.1 U1 R28 in progress.

N 4.1.2 Unit I is in Mode 5 or Mode 6.

2 4.1.3 The Reactor Vessel upper internals are installed.

4.1 .4 The Reactor Vessel upper head is in place.

4.1.5 At least two Core Exit Thermocouples are connected AND functional with readouts on the PPCS.

Ensure high alarms for each thermocouple set at 135 and 195 degrees Fahrenheit.

4.1.6 review4he Conditions and limitations of the RCS are met for entering reduced inventory as defined in Figure 1.

4.1.7 Two Residual Heleat Removal (R1-IR) ]oops shall be operable and one RHR loop shall be in operation.

4.1.8 Post signage for protected equipment, per Attachment A, Protected Equipment for Unit I in Reduced Inventory.

Page 8 of 33 CONTINUOUS USE

POINT BEACH NUC LEAR PLANT O P4F OPIRATING PROCEDURES SAFETY RELATIED Revision I REACTOR COOLANT SYSTEM REDUCED Ma!' 10. 2004 INVENTORY REQUIREIMENTS AND NOZZLE IDAM OPERATIONAL RE-Q UIREMENTS UN'ITl I INITIALS NOTE: Actual assignment of the additional personnel listed below will be directed by the procedure.

4.1.9 Notify Ops Planners and I&C Supervision of the followine additional personnel support requirements w\hilc in Reduced Inventorv:

a. One (I) Control Operator shall be assigned for monitoring RCS inventory and decay heat removal operations.

b. One (1) I&C technician shall be available to support venting of LT-447/447A and to assist Operations personnel with other reduced inventory instrumentation (e.g., RIHR flowv).

c. One (I) Auxiliary Operator shall be available to monitor RIMR pump operation.

4.1.10 RWSTI level is greater than 40%.

4.1.1 1 At least one Narrowv Range RVLIS instrument available.

(LI-496 or LI-497, R-I RV Narrow Range Level Indicator.)

4.2 1-tia-Mnhinens-trhast- A ez-Dam Seetiin 5-4.2.1 OP-4 Seetiovi 5.1 pleied if reqife4 Page 9 of 33 oCONTINUOUS USE

P'OINT1131EACI I NUCLEAR i'l.ANl OP 41 OE'LRAATING PROCEIDURIE:S SAFETY RELATED Revision I REACTOR COOLANT SYSTEIM REDUCEI) M\ay 10, 2004 IN'\ENTORI' REQUIREMI\4ENTIS AND NOZZLE DAM OPER-ATIONAL REQUIREMENTS UNIT I INITlALS 5.0 PROCEDURE CAUTION W'lhen any RCS cold leg temperature is less than or equal to the LTOI' cnabling temperature (270°F) specified in the PTLR, only onc Safety Injection Pump may bc OPERABLE whencvcr the Reactor Vesscl licad is on. TS 3.4.12 CAUTION IF a malfunction of the MIR system occurs whilc pcrforming this procedurc, THEN the actions of SEP'-1, Degraded RIR System Capability, shall he performed.

NOTE: Section 5.1 does not apply if the reactbr is defucled.

5.1 Entering Reduced Inventory Conditions: i 5.1.1 Align one Safety Injection Pump for Upper Plenuum Injection, by performing Substep A OR B:

a. IF IP-]5A is the pump selected for Upper Plenum Injection, THEN ensure:

(1) IP-15A control switch on C-OI is in PULLOUT.

(2) IP-15B breaker IA52-85 on IA-06 is tagged in the Racked Out position.

(3) IP-15A breaker IA52-59 on IA-05 is Racked In.

(4) 1SI-829D. Safety Injection 'lest Line Isolation, is l.OCKED SHUT.

,I Pace IO of 3') fCONTINUOUS USE

1'01N'i 131EACI I NUCLEAR PL'.ANT O1'P41 OP'l.RllATING PROCEDURES SAFETY RELATEl)

Revision I REACTIOR COOLANT SYSTENM REDUCED lMay 10. 2004 INVENI TORY REQUIREMENTS ANID NOZZLE DANM OPERATIONAL REQUIREMENTS UNIT I INITIALS NOTE: The remaining substeps of Step 5.I.1.a ma!

be performed in any order.

(5) OPEN I Sl-829A, P-] SA/B SI Pump Discharge Crossconnect.

(6) OPEN ISI-829B, P-1 SA/B SI Pump Discharge Crossconnect.

(7) 1SI-888A, P-1SA SI Pump Discharge, is LOCKED OPEN.

(8) Ensure a SI pump rccirc flow path exists as followvs:

. Ensure LOCKED OPEN, ISI-876A, P-15A SI Pump Discharge Recire To SI Test Line.

. Ensure OPEN with Air Off and Vented, I SI-897A, SI Test Line Return. __-

. Ensure OPEN wvith Air Off and Vented, I SI-897B, SI Test Line Return Second Off Isolation.

(9) SHUT lSI-878E, P-15B SI Pump Loop A Injection.

(10) SH4UT ISI-878F, P-15B SI Pump Loop B Injection. __ -

NOTE: Core deluge flow is alvays through IP-15B discharge valve ISI-866B regardless of whvich Safety Injection Pump is being used.

(I1) 1SI-866B, Core Dleluge Injection Line Isolation, is SHUT but OPERABLE. _

(12) Suction from the R\ST is available to IP-15A.

(13) SHUT ISI-878B, P-ISA SI Pump Loop B Injection.

(14) SHUT ISI-878D, P-15A SI Pump loop A Injection _

Pge I I of 3 Pae fCON'TINUOlS USE

P'OINTB EACI I NUCLEAR I'LANT 01' 41:

01P'ERATING PROCEDURE S l SAFETY RELATED Revision I REACTOR (O()LANT SYSTEIM REDUCED May 10. 2Q04 INVENTORY REQUIREMENTS AND NOZZLE DAM OPElRATIONAL REQUIREMENTS UNIT I

[NI1'IA LS (15) At least onc Upper Plenum Injection valve is OP'ERABLE: (Mark valve NOT used-N/A, if applicable)

• ISI-878A, P-I5B SI Pump R-1 Reactor Vessel Injection

• lSI-878C, P-15B SI Pump R-1 Reactor Vessel Injection

b. IF IP-I 51B is the pump selected for Upper Plenum Injection, T IlEN ensure:

(1) IP-1513 control switch on C-01 is in l'ULLOUT.

(2) Either of the following conditions is met:

(a) I P- I 5A breaker IA52-59 on I A-05 is tagged in the Racked Out position, OR (b) Ille following three (3) conditions arc met:

(I) lSI-S66A, Cold Leg Injection Line Isolation., is tagged SHUT' with power removed, (2) 1Sl-829A OR ISI-829B. is tagged SHUT (3) IP-15A control switch is in PULLOUT.

(3) IP-15B breaker IA52-85 on lA-06 is Racked In.

NoTE: The remaining substeps in Stcp 5.1.2.b may be performed in any order.

(4) ISI-86613. Core Deluge Injection Line Isolation, is Sl-IUT but OPERAB3LE.

P'aae 12 of 33 CONTINIJOLUS U)SE

POINT I3EACII NU.C'L IEAR PLAN'T OP 40 OPERATING PROCED)UJRES SAFETY RELATE[)l-Revision I REACTOR COOLANT SYSl EM REDUCED May 10. 2004 INVENTORY REQUIREMENTS AND NOZZLE DAIM OPERATIONAL REQUIREMENTS UINIT I INITIALS (5) Suction from the RNN'ST is available to I P-lI 5B.

(6) SHUT I SI-878E, P-1 5B SI Purmp Loop A Injection.

(7) SHUT 1SI-878F, P-S5B SI Pump Loop B Injection.

(8) ISI-888B. P-15B SI Pump Discharge. is LOCKED OPEN.

(9) Ensure a SI pump recirc flow path exists as follows:

. Ensure LOCKED OPEN, ISI-876B, P-15B SI Pumnp Discharge Recire To SI Test Line.

. Ensure OPEN with AIR OrF ANI) Vented.

I SI-897A, SI Test Line Return.

. Ensure OPEN with AIR OFF AND Vented, I SI-897B, SI Test Line Return Second Off Isolation.

(10) At least one Upper Plenum Injcction valve is operable:

(Mark valve NOT used N/A. if applicable)

• 1SI-878A, 1-151 SI Pump R-1 Reactor Vessel Injection

• ISI-878C, P-15B SI Pump R-l Reactor Vessel Injection

5. 1.2 Ensure at least one of the following sources of makeup water to the Reactor Coolant System is available: (Mark unavailable source(s) N/A)

a. l'-33, Refueling \\Water Circ Pump, wvith a suction available from the RWST.

b. One Spent Fuel Pool Cooling Pump (P-12A or P-12B).

c. One Charging Pump (I P-2A, B. C) wvith a suction available from the RWVST.

Page 13cf 333 CONTINUOUS USE

P10INT 13B.ACI 1 NUCLEAR P'LANT 01' 41-OP'ERATING PROCEIDURES SAFETIY RELATED Revision I REACTOR COOLANT SYSTEM REV)DUCEl) \Mav 10. 2004 INV\'ENTORY REQU IRREMENTS AND NOZZILE D)AMI OPERATIONAL REQUIREM ENTS UNIT I INITIALS 0

5.1.3 Twxvo IU IR Loops are OPERABLE per4he-app1ieb1e-TS-4,7 or- )3.4.S.

5.1.4 The Equipment Hatch is installed. __

5.1.5 The Transfer Tube Gate Valve is tagged SHUT.

NOTE: If the upper airlock inner personnel aeccss door is to be placed in a condition where it cannot be closed, (for example, Maintenance on the door), then the mono-rail cannot l)e installed because the outer personnel access door cannot be closed with the mono-rail installed. However, if the mono-rail is to be installed into the upper airlock, then no other activity can be performed w bhich would prevent the upper airlock inner personnel access door from being closed. This does not pertain to the hatch flange protectors.

5.1.6 At least one door of the 66 foot Personnel Access Hatch is capable of being closed.

a. The inner door is operable, OR

b. The mono-rail is NOT installed, AND the outer door is operable 5.1.7 At least one door of the 26 foot Personnel Access H-latch is capable of being closed.

P'agze 14 of 33 ( 1fCONTINU.IOUS UTSE

P(OINT BEACH NUCLEAR PLANT O(P 41 OPERATING PROCEDlJRIES SAFETY RELATEl)

Revision I REACTOR C09LANT SYSTE-M REEDUCED May 10. 2004 INVEN1,TORY' I'EQUIREMENTS AN!) NOZZLE DAM OPERATIONAL REQUIRENIENTS UNIT I INITIALS 5.1.8 Ensure at least one Containment Accident Fan Cooler Unit is available for immediate operation:

12 t

A NOTE: ISWN'-144, IIX-15A-D Cont Recirc IIX SNN'-

2907/2908 Throttle Bypass, AND 1SNNF-176, RE-216 CLIZ Monitor FI-2888 Return Inlet arc SHUT per OP 3C, Hot Standby to Cold Shutdown.

a. Align Service Water for operation of the selected Containment Accident Fan Cooler Unit(s).

b. Ensure the selected Containment Accident Fan Cooler Unit(s)' breaker(s) are racked in.

c. Ensure selected Containment Accident Fan Cooler Units' control switches are in PULLOUT. AND)NOT TAGGED.

5.1 .9 Establish the following support personnel requirements for Reduced Inventory operations, AND track assigned personnel on Attachment C. Support Personnel for Reduced Inventory Operations:

a. One (l) Control Operator shall be assigned for monitoring RCS inventory and decay heat removal operations. Shall NOT be the unit CO. May-av÷ethei-4utes assigned bN i3 X hiftMaageft

b. One (1) I&C technician shall be available to support ventin- of LT-447/447A and to assist Operations personnel wvitlh other reduced inventory instrumentation (e.g., RI-R flow). This person may have secondary duties that allow him to respond whvhen called upon.

c. One (I) Auxiliary Operator shall be available to periodically monitor RHR pump operation. This person shall NOT be the PAB Operator OR a member of the lFire Brigade. Individual will be stationed in the PAB and may have secondary duties assigned by Shift Manager. Those duties shall not prevent individual from responding when called upon (to check pump operation).

Page I 5 of '33 P(ONTINUOUS USE

POINT E3EACI I NUCLElAR PLANT 01 41 OP'ERATRAI ING PROCEDURES SAF--l1.E'Y R1.LATEID Revision I REACTOR COOLAINT SYSTIEM REIDUCEI) Max' 10. 2004 INVENiI ORY REQUIREMENTS ANI) NOZZLE1, DA.M OPEIRATIONAL REQUIREMIENITS UNIT I INI'lTIALS I 5.1.10 Place this procedure in the front of Containment Penetration Closure Notebook.

5.1.11 Continue lowering level per one of the following procedures, as applicable:

• OP 4D Part 1. Draining the Reactor Coolant System.

• OP' 4D Part 3. Draining the Reactor Cavity and Reactor Coolant System.

7- a OP 5A, Reactor Coolant Volume Control 0

NOTE: To install nozzle dams continue with procedure.

5.1.12 Initiate Attachment D, Shiftly Reduced Inventory Checks.

lage 16G of 33 C(P)NTJNI..JOUjS USE

POINT BEAC I1N (CLEAR IPLANT Ol 4F OPERATING PROCEDUlIRES SAFETY RE[..,\11I)

Revision I REACTI'OR COOLANT SYSTE. REDUCIEI) MaI 10. 2001 INVENTORY RElQUIREMENTS'AND NOZZLE DAM OPERATIONAL REQUIREMI 'ENTS UNirT I

_ INITIALS 0

0 5.2 Nozzle Dam Installation Requirements: Dis}fe-fallIwin-epefatieonal reo remes are metpier-4o istaflhng4asl-h etc" e-damm1 5.2.1 One SI pump disabled for LTOP.

5.2.2 The available SI pump's control switch in PULLOUT.

5.2.3 Both SI pumps discharge valves SHUT.

a. lSI-866A, Cold Leg Injection Line Isolation

-4lb. ISI-866B, Core Deluge Injection Line Isolation_

5.2.4 One of the following vent paths established:

a. Reactor Vessel head raised to greater than or equal to 1 inch above reactor vessel flange, OR removed.

b. Pressurizer mnanwav removed AND Reactor shutdown for greater than 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.

c. BOTH Pressurizer code safeties removed ANI) Reactor shutdown for greater than 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

NOTE: The equipment listed on Attachment B shall be posted A.NI) protected for the duration of time that nozzle dams are installed.

5.2.5 Ensure signage posted for protected equipment, per Attachment B, Protected Equipment While Steam Generator Nozzle Dams are Installed.

5.2.6 WHT-EN the above requirements are met, THEN permission may be granted to install last-hot4egnerozzle dams.

0 1 5.2.7 WHEN insialled, 0 THEN initiate monitoring nozzle dams in accordance with 01 1 1, Steam Generator Nozzle Dam Operation Guide.

5.2.8 Go to Section 5.3, Nozzle Daam Requirements While Installed.

. ~,

Pa<ge 17 (f 33 eC()NTINUOUS USE

POINT BEACI INUCLEAR PLANT OP 41 OPERA1TING PRO(OCEDURES SAFETY RIELA I tI)

Revision 1 REACTOR COOLANT SYSTEM REDUCED Mvlay 10. 2004 INVENTORY REQUIREIMENTS AND NOZZLE I)AMN OPERATIONAL REQUIREMENTS UNIT I INITIALS 5.3 Nozzle IDam Requirements While Installed: (11-4)

5. 3.1 WHEN the RX Vessel head is on.

• - THEN the following conditions shall be met.

a. One SI pump disabled for LTOP.

b. The available SI pump's control switch in PULLOUT.

c. B3OTH SI pumps discharge valves SHUT.

.

• SI-866A, Cold Leg Injection Line Isolation

• . S1-866B, Core Deluge Injection Line Isolation

,2 9 5.3.2 WNIHEN the Reactor Vessel head is removed.

THEN the following conditions shall be met.

NOTE: Thc SI pump control switch may he removed from PULLOUT for approved testing (e.g., IT 760),

providcd the reactor vesscl head is removed.

a. BOTH SI pump control switches in PULLOUT.

l IP-15A-CS a IP-15B-CS NOTE: The SI pump discharge valve maiy be opened for approved testing (e.g., IT 760), provided the reactor vessel head is removed.

b. BOTH SI pump discharge valves SHUT.

. 1SI-866A, Cold Leg Injection Line Isolation.

I ISI-86613, Core Deluge Injection Line Isolation.

Uv Page I 8 of 33 C:ONTINUOUS USE.

POINT 31EACI I NUCLErAR PLANT Oil 41:

OPEIRATING PROCEDURIES SAFETY RELAI E-l)

Revision I REACTOR COOLANT SYSTEM REDUCED May 10, 2004 INVENTORY REQUIREMENTS AND NOZZLE DANM OPERATIONAL REQUIREMENTS UNIT I INITIALS 5.3.3 One of thc following vent paths maintained:

a. Reactor Vessel head raised to greater than or equal to I inch above the reactor vessel flange. OR removed.

b. Pressurizer manwav removed AND Reactor shutdown for greater than 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.

c. Both Pressurizer code safetics removed ANI) Reactor shutdown for greater than 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

NOTE: The equipment listed on Attachment B shall be posted A.sI) protected for the duration of time that nozzle dams are installed.

5.3.4 Continue requirements for maintaining protected equipment, per Attachment B, Protected Equipment While Steam Generator Nozzle Dams are Installed.

5.3.5 Continue monitoring nozzle dams in accordance with 01 I 1, Steam Generator Nozzle Dam Operation Guide.

5.3.6 Initiate Attachment E, Shiftly Nozzle Dam Checks.

, I Pag~e l 9 of .31 CONITNUOUS USE

POINT BEACH NUCLEAR PLANT OP 41:

OPERATING J PROCEDIURIS FiTY I ELAl [)

Revision 1 REACTOR COOLANT SYSTEM1 RED)UCED) Mlav 10. 2004 INVENTORN REQUIREIMvIENTS ANI) NOZZLE )AIM OPERATIONAL REQUIREINIH NTS UNIT I INITIALS NOT'E: An air lealk, from a nozzle dam, into the col(l leg could force water from the vertical section of the steam generator cold leg bhack to the vcssel. Because of this, when either cold ltc nozzle (damnl is depressurized for removal, the operator should be nvare of the possibility of an inventory transfer to reflood the vertical section of the Pipe. This could be as much as 305 gallons per cold leg.

5.4 Nozzle Darn Removal Zr 5.4.1 Wh11EN removing nozzle darns, o TllEN perform the following:

a. WEIIEN Equipment listed in Attachment 13 is no longer required to be protected for nozzle dams.

TI-IT EN remove protected equipment signage while continuing with this procedure.

b. Ensure reactor vessel level at 22-25% on I LI-447/447A.

c. NV'hlEN the above requirement is met, ThI IEN permission may be granted to remove a hot leg nozzle darn first.

Paue 20 of 33 CONIFINUOIJS USE

POINT I3IFA(I I NUCL.EAR PLANT OP 41:

OPERATING PROCEDURElS SAFE REI'L.ATED)

Revision I REACTOR COOLANT SYSTEIM REDUCED M\1ay 10'2004 INVENTORY REQUI REM ENTS ANI) N OZZLE DAIM OPERATIONAL REQUIREMENTS UNIT 1 INITIALS NOTE: Section 5.5 does NOT apply if the reactor is defueled.

5.5 Termination Of Reduced Inventory Condition WHEN Reactor Vessel level has been raised to ureater than 55%.

THEN perform the following to terminate Reduced Inventory condition:

NOTE: The SM may N/A an) of the following steps based oil plant conditions.

5.5.1 Release additional support personnel for Reduced Inventory operations, AND) terminate tracking assignments on Attachment C, Additional Support Personnel for Reduced Inventory Operations 5.5.2 Ensure Containment Accident Fan Cooler switches are in PULLOUT.

5.5.3 IFdesired, I THEN SHUT Service \Water valves for the Coniainment Accident Fan Coolers (refer to OP 3C, I-lot Standby to Cold Shutdown):

ISW-144, IIX-15A-D Cont Recirc iIX SWN7-2907/2908 Throttle Bypass ISW-176, RE-216 CLR Monitor F1-2888 Retumn Inlet Pag~e21 of 333 Pag2 o33CONTINUOUS USE

POJNT BEACIH NUCLL.lAR PLANT Ol' 41 OPERATING PROCEI)URES SAFETY R1 AT1 l)

Revision I REACTOR COOI.ANT SYSTEM REDUCEI) Mlay 10, 2004 INVENTORY REQUIREMENTS AND NOZZILE DAM OPERATIONAL REQUIREMENTS UNIT I INITIALS NOTE': The following -alves may have been repositioned during the initial conditions dependent upon which Safety Injection flow path was selected

• lSI-829D, Safety Injection Test Line Isolation

• ISI-829A,P-15A1B SI Pump l)ischargc Crossconneet

• lSI-82913,1'-15A/B SI Pump Discharge Crossconnect

• lSI-888A, P-15A SI Pump D)ischarge

• lSI-88813, P-15B SI Pump Discharge

• ISI-878E, P-15B SI Pump Loop A Injection

• lSI-878F, P-1 5B SI Pump Loop 13 Injection

• ISI-87813, P-1SA SI Pump Loop 13 Injection

• ISI-878D, 1-15A SI Pump Loop A Injection

• • SI-866A, Cold Leg Injection Line Isolation

• ISI-866B, Core Deluge Injection Line Isolation 5.5.4 Align the applicable portions of the Safety Injection Syslem per CL 7B, Safety Injection System Checklist.

5.5.5 Remove protected equipment signage from equipment listed in Attachment A.

Page '2 of 33 CONTINUOUS USE

I POJNT BEACH NUCLEAR PLANT OP 4F OPERATING PROCEI)URIES SAFIETY RlIl.ATE1)

Revision I REACTOR COOLANI SYSTEM REDUCEI) Mam 10. 2004 TNVENTORY REQUIRENIENTS ANi) NOZZLE DANI OPERATIONAL REQUIREMENTS UNIT I

6.0 REFERENCES

6.1 Technical Specifications 6.1.1 3.1.1, Shutdown Margin (SI)MN) 6.1.2 3.3.6, Boron Dilution Alarm

6. 1.3 3.4.8, RCS Loops-Mode 5, Loops Not Filled 6.1.4 3.4.12, Lowv Temperature Overpressure Protection (LTOP) System 6.2 Procedures 6.2.1 CL 7B, Safety Injection System Checklist 6.2.2 NP 10.3.6. Outage Safety Review and Safety Assessment 6.2.3 01 I1, Steam Generator Nozzlc Dam Operation Guide 6.2.4 01 163, Si, RI IR and CS Pump Runs, and Venting Si Pump Casings,'.

6.2.5 OP 3C, Hot Standby to Cold Shutdown 6.2.6 OP 4D Part 1. Draining the Reactor Coolant System 6.2.7 OP 4D Part 3, Draining the Reactor Cavit' and Reactor Coolant System.

6.2.8 OP 5A, Reactor Coolant Volume Control 6.2.9 SEP-I. Degraded RIHR System Capability 6.2.10 SEP-3.0, Loss of All AC Power to a Shutdown Unit 7.0 BASE!S I B-I Generic Letter 88-1 7. Loss of Decay Heat Removal.

B-2 VPNPD-88-635, "Response to GI, 88-17, Loss of Decay lleat Removal," dated 12/30/88 B-3 VPNPD-89-061, "Response to GL 88-17, Loss of D)ecay Heat Removal," dated 2/2/89 B-4 CAP055585, Improvement to Hot Leg \'ent Path Controls Required Page 23 of 33 CONTINUOUS USE

POINT BEACIH NUCLEAR PLANT OP 4F:

OPERATING PROCEDURES SAFETY RELATED Revision I REACTOR:QOOLANT SYSTEM REDUCED May 10. 2004 INVENTOaY REQUIREMENTS AND NOZZLE DAM OPERATIONAL R.EQUIREMENTS UNIT I REMARKS:

II Pace 24 of 33 CONTINUOUS USE

POINT' BEACIlI NUCL11EAR P'LANT 01 '41:

OPER-ATING PROC(:EDUR17S SAFEITY RELTE!)

Revision I REACTOR COOLANT SY STEM RIEDUCELI) ;Mav 10. 2004 INVTENTORY' REQUIREiME1 NTS AND) NOZZLE DA%?\MI OPERATIONAL REQUIRl ;EMElleNTS UNIT I Figure 1 Reactor Coolant System Reduced Inventory Requiremients NOTE: Not a:pplicable for no7zzc (himi rclquirecniets see al)rol)wiate sections for requirenients.

EI9flZ No

- //Fuel in Yes Vessel  ?

~- _ ' 1-lot leg vent,,

There are no -- \path acceptable>

contaiment closure or ! No Note / Yes reduced inventory I requirements for this, condition I

/\\

/ '

7\\ /

o Cold Leg\ // Containment closure\

Yes Opening No

_Oei o '- 'able to be accomplished priorr.

>1 SQ IN tTimeTo Boil (TTB)

Yes Note 2 Ref CL-1 E V

Reduced inventory entry is not allowed L No \ ,/

in this condition.

Reduced inventory entry is allowed in this condition.The Ability to maintain containment closure within time to boil is also required.

Page 25 of 33) CONTINUOUS USE

POINT BIACI I NIUlE1AR P'l'ANT O1 41P OPERATING i'PRCED1URES SAFETY R N FlD Revision I REACTOR COOlANT SYSTL-M REDUCEI) Mav 10. 2004 INVENTORY Rl.QUIREIMENhSANI) NOZZlE DAI\M OPERATIONAL- REQUIREMENTS UN IT I Figure I Reactor Coolant System Reduced Inventory Requirements continued 0

NOTE 1: ACCEI'TABLE HOT LEG VENT PATHIS

• A steam generator hot leg manwav opening is acceptable if its hot leg nozzle dam is not installed.

• A steam generator cold leg manway opening is acceptable if its hot leg nozzle dam is not installed and its tube bundle is drained.

• The Reactor Vessel head raised to greater than or equal to 1 inch above the Reactor Vessel Flange is acceptable.

• The Pressurizer manway opening is acceptable if the Reactor has been shut down for greater than or equal to 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.

• Both Pressurizer code safeties removed is acceptable if the Reactor has been shut down for greater than or equal to 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

NOTE 2: COLD) LEG OPENINGS

• A single pipe with an inside'diameter of less than or equal to 1-1/8 inches has a cross-sectional area of less than 1 square inch.

• If a pipe with an inside diineter of less than or equal to 1-1/8 inches has a coupling or other fitting attached which has a cross-sectional area greater than I square inch, then the effective cross-sectional area is less than 1 square inch and is acceptable.

• Working the RCJ's oln their backseat without a hot leg yent is acceptable provided thal the lab seal AP during previous normal operating conditions meets the following criteria (Data from previous logs during normal at power conditions):

• To work one pump, its lab seal AP during normal operating conditions is required to have been greater than or equal to 5 inches water.

• To work two pumps, their lab seal AP during normal operating conditions are required to have been greater than or equal to 20 inches water.

• IF the above con(Jitions are not met, THEN to work a RCP on its back-seat without a ]hot leg opening requires further evaluation.

Page 26 of 313) CONTINUOUS USE

POINT B-AACI I NUCLEAR PLANT OP 4F OPERATING PROCEI)URIES SAFETY RELATF.1)

RCvision I REACTOR COOLANT SYSTEIM REDUCED Mlav 10. 2004 INVENTORY REQUIR EMENTS AND NOZZLE7 1)AMi OPERATIONAL REQUIREMENTS UNIT I Attachment A Protected Equipment For Unit I In Reduced Inventor,\

NOTE: Work on protected equipment is prohibited. Work prohibite(l on protected equipment is defined as those activitics involving intrusivc wvork on or external contact with the equipment. Activities performed by Operations to monitor the operation or condition of protected equipment is NOT wvork on protected equipment. (Refer to NP 10.3.6) 0 a NOTE: The Shift M11anager will determine if any activity can be performed on a piece of 8_ protected equipment:- NO-or-shs ll-beperfor-mei-onproteeted-equipmeie- nless-the N worl--l-ot--effeet-ts-operation. as long as this wvork doesn't render the equipment unavailable 2

I- Install Protected Equipment signs and/or restrictions at the following equipment:

Protected Equipment Initials lP-lOA. RHR pump cubicle IP-10B. RIR pump cubicle _

IP-IIA and lP-I11B pump area Selected SI pump (Circle selected pump) IP-15A OR IP-1 5B Selected SI pump suction valve from RWST (Circle select valve) 1SI-896A OR I SI-896B Either SI pump suction from RWST (Circle one) I SI-825A OR I SI-825B Selected SI pumlp discharge valve (Circle selected SI pump v'alve)

I SI-888A OR I SI-888B SI pump discharge valve I SI-866B CC\W heat exchanger area Service Water pump area 1A05, 4160V AC area lA06, G03 Switchgear Room 1B03, Cable Spreading Room IB04. Cable Spreading Room 1B32, 8' PAD _ _ -

I B42, 26" PAB _

EDG aligned to lA05 (Circle One) GOI OR G02 EDG aligned to IA06 (Circle One) G03 OR G04 I YO I red instrument bus IY02 blue instrument bus I Y04 yellow instrument bus Selected Containment Accident Fan (Circle One)

IWIAI OR iWIBI OR INVICI OR I\VIID)

Selected makeup source (Circle One)

P-33 OR IP2A OR 1P213 OR IP2C OR P-129 Reactor Vessel Level Instruments I LT-447 AND I LT-447A U U S

. ag 27 o 3=O.N Page 27 of.33 CONtTINUOUS UlSF

POINT BEACII NUCLEAR PLANT OP 41:

OPERATING P'ROCEDURIES SAFETY RELATEI)

Revision I REACTOR COOLANT SYSTlEhM REDUCED  ;; May 10, 2004 INVENTORY REQUIRl REMMENTS AND NOZZLE 7 AM OPERATIONAL REQUIREIMENTS UNIT I Attachment A Protected Equipment For Unil I In Reduced Inventor%

NOTE: The following equipment is "protected cquipmcnt" while in Reduced Inventory.

Train A RHR Train B RHR Train A CCW including required CC H-Xs Train B CCWN' including required CC I-IXs IA05 4160 VAC bus IA06 4160 \VAC bus IB03 480 VAC bus IB04 480 VAC bus IB32 480 VAC bus IB42 480 VAC bus 5 Service water pumps Service water piping which supplies CC l-IXs on 46' el. PAB One train SI to establish Upper Plenum Injection w ith a suction from the RIMST with level greater than 40%

IYOI red instrument bus IY02 blue instrument bus I Y04 yellow instrument bus I LT-447 RV level transmitter I LT-447A RV level transmitter Train A EDG aligned to IA05 Train B EDG aligned to IA06 One containment accident fan wvith service water supply One of the following makeup sources:

a P-33 refueling water circ pump with suction from the R\VST wvith level greater than 16%

1P2A charging pump with suction from the RW'ST with level greater than 16%

IP2B charging pump with suction from the RWST with level greater than 16%

1P2C charging pump with suction from the RWST vith level greater than 16%

P- 12 SEP cooling pump PaLge 28 of 33) Pe8fCONTINUOUS USE

POIN I131ACII NtUCLl-AR1'1 PLANT 01' 41 OPERATING PROCED1URES SAi:}.Y RELATED)

Revision I REACTOR COOLANT SYSTEM REDUCED Mav 10. 2004 INVENTORY REQ UIREi ENTS AND NOZZLE I)AI OPERATIONAL REQUIRENIENTS UNIT I Attachment B Protected Equipment While Steam Generator Nozzle Dams Are Installed NOTE: The following equipment is "protccted equipment" while Steam Generator Nozzle Dams arc installcd.

NOTE: W'ork on protected equipment is prohibited. WVork prohil)ited on protected cquipment is defined as those activities involving intrusive work on or external contact vith the equipment. Activities performed by Operations to monitor the operation or condition of protected equipment is NOT wvork on protected equipment. (RZefcr to NP 10.3.6)

NOTE: The Shift Mlanager will determine if any activity can be performed on a piece of protected equiplment.- NO-w-ork-shsll-a-berformein-proteeted-equipmnent-u.nes-*the or-ill-not-affeciits-oper-ation. as long as this work doesn't render the equipment unavailable Install Protected Equipment signs and/or restrictions at the follo'ving equipment:

= Protected E quipment Initials Reactor Vessel Head raised greater than or equal to I inch, One of the following OR removed.

Hot Leg V'ent Paths:

A (Mark Venon-aplcb Pressurizer Manway Removed.

(Mark; non-applicable vent paths "N/A") (B-4) Both Pressurizer Code Safeties Removed.

B Unit I Steam Generator "A" Nozzle Dam Panel C Unit I Steam Generator "B" Nozzle Dam Panel D K-3A Service Air Compressor E K-3B Service Air Compressor P'age 29 of 33 oCONTINU(OIJS USE

POIN'I BEACH NUC1E1AR PLANT OP 41 OPERAIiNG PROCEDUlRES Revision I REACTORt COOLANirT SYSTrI I ;M\RD IDUCE D Mla~v.;0, T

2004 INVENT1 ORY RlEQUIREMENNTS AND NOZZLE DANM OPERATIONAL REQUjIREMN\ENITS UN IT I Attachment C Additional Support Personnel For Reduced Inventory Operations NOTE: 1Therc shall be one (1) person assigned to each of the following positions at all times whilc in Reduced Inventory operations.

• One (1) Control Operator shall be assigned for moniioring RCS inventory and decay hbcat removal operations.

• One (I) I&C technician shall be available to support venting of LT-447/447A and to assist Operations personnel with other reduced inventory instrumentation (e.g.,

RIIR11 flow).

• One (I) Auxiliary Operator shall be available to monitor RIIR pump operation.

Control Op rator I&C Technician Auxiliary 0p erator Name Date Name I)ate Name Date Page 310 of 33) CONTINUIOUS I SE

• NT BEACH NUCLEAR PLANT OP 4F uieERATING PROCEDURES SAFETY RELATED Revision I REACTrOR COOLANT SYSTEM REDUCED May 10, 2004 INVENTORY REQUIREMEINTS AND NOZZLE DAM OPERATIONAL RliQUIRIEMEN'rS UNIT I Attachment D Shiftly Reduced Inventory Checks Condition JDate/Time IDate/Timc TDate/Time f Date/Time Daterrime Daterl'ime Date/Time At least two core exit thjernmocouplcs are connected and functional with readouts on the PPCS.

Two residual heat removal (RlIR) loops shall be operable and one RHIlt loop shiall be in operation.

Reactor vessel upper head is in place.

Reactor vessel upper internals are installed.

0 Unit I RWST level is greater than 40%.

C Equipment hatch is installed 0

IC

[Transfer tube gate valve is tagged SHUT At least one door of tlie 66 foot personnel access hatch is capable ofbeing closed. (see note 1)

At least one door of the 26 foot personnel access hatch is capable of being closed Ensure at least onc containment accident fan cooler unit is available for immnediate operation At least one Narrow Range RVLIS instrument available 1L-496 or LI-497, R-l RV Narrow Range ILevel Indicator

! -- IIiti-ls I I_

IPage 31 of 33 CONTINUOUS USE

,NT BEACH NUCLEAR PLANT OP 4F OPERATING PROCEDURES SAFETY RELATED Revision I REACTOR COOLANT SYSTFM REDUCED 'May 10, 2004 INVENTORY REQUIREMENTS AND NOZZLE DAM OPERATIONAL REQUIREMENTS UNIT I Attachment D Shiftly Redtiuced Inventory Checks I Condition TDate/Time Date/Time IDate/Time Date/Timne IDate/TimenI I)atefrimne j

Date/Timre I Shift Managemcnt Review CL I E for ability to meet containment closure prior to Time To Boil (1TB) .

Initials I NOTE I: If upper airlock inner personnel access door is to be placed in a condition wherc it cannot be closed, (for example, Maintenance on the dloor), then mono-rail cannot be installed becausc outer personnel access door cannot bc closed with mono-rail installed.

JIlowever, if mono-rail is to bc installed into upper airlock, then NO other activity can be performed which would prevent upper airlock inner personnel access door from being closed. This does not pertain to hatch flange protectors.

Page 32 of 33 CONTINUOUS USE

I NT BEACH NUCLEAR PLANT OP 4F OPERATING PROCEDURES SAFETY RELATED Revision I REACTOR COOLANT SYSTEM REDUCED May 10, 2004 INVEINTORY REQUIREMENTS AND NOZZLE DAM OPERATIONAL REQUIREMENTS UNIT I

- Attachment E-Shiftly Nozzle Dam Checks NOTE: The SI pump control switch may be removed from PULLOUT for approved testing (e.g., IT 760), provided the reactor vessel head is removed.

Page 33 of 33 CONTINUOUS USE