ML030870822
| ML030870822 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/29/2002 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0094 AOP 23, Rev 0 | |
| Download: ML030870822 (20) | |
Text
Nuclear Power Business Unit G ,..O T-e"- - SA.C 7 TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3. Temporary ProcedureChanges,for requirements. Page 1 of I - INITIATION Doc Number AOP 23 Current Rev 0 Unit PB13 Temp Change No. 2002-0752 Document Title Establishing Alternate AFW Suction Supply Existing Effective Temporary Changes N/A Brief Description Add AFW Minimum Flow requirement fold out page Criteria (Identify specific changes on Form PBF-0026c, Document Review and Approval Contnuaton. and include with the package) 0 Initiate PBF-0026h and include with the change.
Other documents required to be effective concurrently with the temporary change: i /4 Changes pre-screened according to NP 5.1.8? 0 NO El YES (Prid documentation according to N 51.8)
Screening completed according to NP 5.1.8? El NA 0 YES (amch copy)
Safety Evaluation Required? 0 NO [I YES (if Yaresion may proce=. ortfnates anda,,alssAl1 be fo plemenng)
Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions.
(If any answers are YES, a revision may be processed or final reviews and approvals shall be obtained before implementing)
Will the proposed change: YES NO
- 1. Require a change to, affect or invalidate a requirement, commitment, evaluation or description in the Current or ISFSI Licensing Basis (as defined in NP 5.1.8 and NP 5.1.7)? E]
- 2. Cause an increase in magnitude, significance or impact such that it should be processed as a revision?
- 3. Delete or modify a prerequisite, initial condition, precaution, limitation or other steps that could have safety significance or affect the procedure's margin of safety?
- 4. Delete QC hold points, Independent Verification or Concurrent Check steps without the related step(s) that require the performance also being deleted?
- 5. Change Tech Spec or other regulatory acceptance criteria other than for re-baselining purposes? [] 21
- 6. Require a change to the procedure Purpose or change the procedure classificatjon? 0 Initiated By (print/sign) Ross Groehler / ( "* Uate 10/29r2002 II - INITIAL APPROVAL This change is correct and complete, can be performed as written, and does not sely affect personnel or nuclear safety, or Plant operating conditions.
Group Supervisor (print/sign) 1/
,4~2Ž Dt (Cannot be t1e Initiator) '*'
This change does not adversely affect Plat rating conditions. ir~elated procedures only)
Senior Reactor Operator (print/sign) -J Ž_
,_)"I ) / 1A
/- Date I / O-6 (Cannot be the Initiator or Group Supervisor)
IH - PROCEDURE OWNER REVIEW EX Permanent El One-time Use [I Expiration Date, Event or Condition:
El Hold change until procedure completed (final review and approval still required within 14 days of initial approval)
El QRIMSS Review NOT Requireýd* min/NNSR only) [ QR Review Re *red 0l MS & Requ, efcmcc NP ,.6)
Procedure Owner (rnsg s, -- Dte cýr This Change and suooorting recuirements correctly comoleted and processed IV- AVL REVIEW AND APP? ,'AL (Must be comoleted within 14 days of initial aot l he Initiator. OR and ATrorv ilutho tv s be indeoendent from e ch th 'I S SS (print/sipn) I Q 6\Xe%) LO D I ) Date 6 Indicates 50.59/72 48 applicabihty assessed, any necessary screenings/evaluatens performed, determinati n made as to whethe addiuf al cross-disciplinary review required, and if required, performed. I]* [*
MISS Meeting No. _ -- /.k Atoroval Authoritvy orintisizo " 1..C_ ti ) tj',*-/,'/Date / 0-' 42..
V - REVISION INFORMATION FOR PERMANENT C/ANGES \ -
PostTyping Review, (pit/ign Date l7, Indicates temporary change(s) incorporated exactly as approved and no other changes made to document.
Incorporated into Revision Number Effective Date PBF-0026c References- NP 1.2 3 Revision 13 01/16102
Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page -__o_
Doc Number AOP 23 Revision 0 Unit PBI Title Establishing Alternate AFW Suction Supply Temporary Change Number 2002-0752 Description of Changes:
Step
- Change/Reason Add AFW minimum flow requirement: Monitor and maintain minimum AFW discharge flow or stop the affected AFW pump as necessary to control S/G levels. See SCR 2002-0458, CAP029908, P-38A MD Foldout Page AFWP has inadequate Recirc Flow during IT-=10.
Other Comments
- Note- Recording of Step Number(s) is not required for multiple occurrences ofidentical information or when not beneficial to reviewer-.
PBF-0026c Revision 6 04/18/01 References NP 1 1 3, NP 1 2.3
Poent Beach Nuclear Plant TENIPORARY CHANGE AFFECTED MIA.NUAL LOCATION Page of Procedure Number AOP-23 Revision 0 Unit PBI Title ESTABLISHNG .ATERINATE .AFV SUCTION SUPPLY Temporary Change Number 2002-0752 I - LEVMI*DL~kTELY AF"TER EN"ITIAL (after Final .A-PPROV.,.L ON PBF-0026e (Non-Intent Approval if changec of changes) itente mvol*ed)
This procedure chancre has been processed as follows: (Manual/Location) Date
'] Copy included in work package for field implementation. (WO, Performed NO.)
Copy filed in Control Room temp change binder (Operations only).
" Z¶'. Z..
[] Original change package provided to -t-6 V to obtain Procedure Owner Review (e.g.. Owner review may be coordinated by In-Group OA I1,Procedure Writer, Procedure Supervisor, etc) /O 2 '-o Performed By (print and sign) ýS Sc" 4 ' / Date Z f0 - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA II, Procedure Writer, etc.)
This procedure chancre has been processed Im as follows: (M~anual/Location) Date Performed EM Copy sent to Document Control Distribution Lead for Master File.
/ .**
WJ (Not required f'or one-time use change)
El Copy filed in Group satellite file. (Not required for one-time use changes.)
EL Copy filed in Group one-time use file.
[] Original Temp Change provided to *: .,to obtain Final Approvals /-Z,- 2.
(e.g. final approval may be coordinated by In-Group OA 11, Procedure Wrier. Procedure Supervisor, etc)
I o('*SL.°p D~ S~-cc{~ LT- OrLE LI0 -"
Performed By (pnint and sign)
, ýDa te PBF-0026h Revision 5 06/13101 I
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) VerIfy SCR number on all pages Page 1 Title of Proposed Activity: AFW minimum flow requirement change to AOP, EOP, CSP, ECA, SEP, 01-62 A/B procedures Associated Reference(s) #: Removal of internals from AF-l 17 and upgrade open function of AFW pumps minirecirc vlaves to safety -related (MR 02-029); SCR 2002-005-01 EOP/ARP actions for AFW"mini-recirc requirement ; 2002-0055, P-38A/B mini recirc flow orifice replacment (MR 99-029 *A, *B);
Flowserve Corporation Pump Division letter dated March 2, 20012; CAP 29908; CAP 29952 Prpaedby Eric A. Schmiddt / John P. Schroeder __ate:
4 Name (Print) "&/ " )I Reviewed by: _ _ _ __
Name-( Print)
,_ __ __ A_ _
Signature
_ _ _ Date: j PART I (50.59/72.48) - DESCRIBE THE PROPOSED ACTIVITY AND SEARCH THE PLANT AND ISFSI LICENSING BASIS (Resource Manual 5.3.1)
NOTE: The "NMC 10 CFR 50.59 Resource Manual" (Resource Manual) and NEI 96-07.
Appendix B. Guidelines for 10 CFR 72.48 Implementation should be used for guidance to determine the proper responses for 10 CFR 50.59 and 10 CFR 72.48 screenings.
1.1 Describe the proposed activity and the scope of the activity being covered by this screening.
(The 10 CFR 50.59 / 72.48 review of other portions of the proposed activity may be documented via the applicability and pre-screening process requirements in NP 5.1.8.) Appropriate descriptive material may be attached.
This screening supports procedural uprgrades to address the Auxiliary Feedwater (AFW) System issue as identified in CAP 29908 and CAP 29952. Procedural guidance for operation of AFW System will be changed such that the operator must ensure that discharge flow for P-38 A/B must be greater than 50 gpm and 1/2 P-29 discharge flow must be greater than 75 gpm. If pump flow cannot be maintained within these requirements, the pump must be secured.
1.2 Search the PBNP Current Licensing Basis (CLB) as follows: Final Safety Analysis Report (FSAR),
FSAR Change Requests (FCRs) with assigned numbers, the Fire Protection Evaluation Report (FPER), the CLB (Regulatory)
Commitment Database, the Technical Specifications, the Technical Specifications Bases, and the Technical Requirements Manual. Search the ISFSI licensing basis as follows: VSC-24 Safety Analysis Report, the VSC-24 Certificate of Compliance, the CLB (Regulatory)
Commitment Database, and the VSC-24 10 CFR 72.212 Site Evaluation Report. Describe the pertinent design function(s),
performance requirements, and methods of evaluation for both the plant and for the caskfISFSI as appropriate. Identify where the pertinent information is described in the above documents (by document section number and title). (Resource Manual 5.3.1 and NEI 96-07, App. B, B.2)
FSAR 10.2 Auxiliary Feedwater System (AF) - The AFW system shall automatically start and deliver adequate AFW flow to maintain adequate steam generator levels during accidents which may result in main steam safety valve opening, such as: Loss of normal feedwater (LONF) and Loss of all AC power to the station auxiliaries (LOAC).
AFW system shall also deliver sufficient flow to the steam generators supporting rapid cooldown during such accidents as: steam generator tube rupture (SGTR) and main steam line break (MSLB).
Each pump has an AOV controlled recirculation line back to the condensate storage tanks to ensure minimum flow to prevent hydraulic instabilities and dissipate pump heat.
TS 3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3.4 Manual AFW Flow Control During Plant Shutdown Manual control of steam generator water level using the AF pumps to remove reactor decay and sensible heat.
FPER 6.6.4 Auxiliary Feedwater System The Auxiliary Feedwater Pumps are provided with a mini-recirc line to ensure a minimum amount of flow is established to keep the pumps from dead heading.
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59172.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 2 FSAR 10.2 Auxiliary Feedwater System (AF)
TS 3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3.4 Manual AFW Flow Control During Plant Shutdown FPER 6.6.4 Auxiliary Feedwater System 1.3 Does the proposed activity involve a change to any Technical Specification? Changes to Technical Specifications require a License Amendment Request (Resource Manual Section 5.3.1.2).
Technical Specification Change : El Yes Z No If a Technical Specification change is required, explain what the change should be and why it is required.
1 1.4 Does the proposed activity involve a change to the terms, conditions or specifications incorporated in any VSC-24 cask Certificate of Compliance (CoC)? Changes to a VSC-24 cask Certificate of Compliance require a CoC amendment request.
El Yes 0D No If a storage cask Certificate of Compliance change is required, explain what the change should be and why it is required.
_-- 10 CFR 50.59 SCREENING PART H (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGN FUNCTION (Resource Manual 5_3.2)
Compare the proposed activity to the relevant CLB descriptions, and answer the following questions:
YES NO QUESTION ED E Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited in the Safety Analyses?
El Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses?
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?
ED El Does the proposed activity involve CLB-described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications?
El 0 Does the activity involve a method of evaluation described in the FSAR?
El 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
El 0] Does the activity exceed or potentially affect a design basis limitfor afissionproduct barrier(DBLFPB)?
(NOTE: If THIS questions is answered YES, a 10 CFR 50.59 Evaluation is required.)
If the answers to ALL of these questions are NO mark Part III as not applicable, document the 10 CFR 50.59 screening in the conclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening Questions.
f any of the above questions are marked YES, identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 3 MR-02-029 upgraded the open function of the AFW pumps mim-recirc AOV to safety-related. The safety-related boundary includes the recirc orifice and all associated upstream components and piping. It is postulated that a failure of the piping downstream of the recirc orifice will not have any adverse affects on the AFW system. The availability of the recirculation flowpath provides an additional flowpath to support minimum flow requirements. This procedure change will improve the reliability of the AFW pumps by not relying upon the recirc flow path for operability as it has been concluded that the restrictions in the recirc orifice may not be adequate for use. Whereas current guidance mandates that the operator verify the position of the recirc AOV and the status of the Instrument Air system, these procedural changes will only require the operator to monitor pump discharge flow.
PART HI (50.59) - DETERMINE ,WHETHERTHE ACTIVITY INVOLVES ADVERSE EFFECTS (Resource Manual 5.3.3)
If ALL the questions in Part II are answered NO then Part mI is E 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 111.3.
1I. 1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION El [] Does the activity adversely affect the designfunction of an SSC credited in safety analyses?
El [] 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 N describe the basis for the conclusion (attach additional discussion as necessary):
Minimum flow requirements will be maintained within recommendations from the vendor by monitoring pump discharge flow and securing the pump as required. Starting and stopping of the AFW pumps has been previously evaluated in 50.59 Evaluation 2002-005, which addressed procedural changes to reduce the potential of pump damage as a result of the loss of the recirculation flow path.
111.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are Z NOT APPLICABLE.)
YES NO QUESTION El El Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB?
El E] Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in the CLB?
If any answer is YES, a 10 CFR 50.59 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion, as necessary).
111.3 TESTS OR EXPERIMENTS If the activity is not a test or experiment, the questions in III.3.a and III.3.b are Z NOT APPLICABLE.
- a. Answer these two questions first:
YES NO QUESTION El , El Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB?
El El Are the SSCs affected by the proposed test or experiment isolated from the facility?
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR numberon all pages Page 4 If the answer to BOT_ H questions in V.3.a is N continue to III.3.b. If the answer to EITHER question is YES then describe the basis.
- b. Answer these additional questions ONLY for tests or experiments which do NOT meet the criteria given in III.3.a above.
If the answer to either question in III.3.a is YES, then these three questions are [] NOT APPLICABLE.
YES NO QUESTION El El Does the activity utilize or control an SSC in a manner that is outside the reference bounds bf the design bases as described in the CLB?
El El Does the activity utilize or control an SSC in a manner that is inconsistent with the analyses or descriptions in the CLB?
E] El Does the activity place the facility in a condition not previously evaluated or that could affect the capability of an SSC to perform its intended functions?
If any answer in III.3.b is YES, a 10 CFR 50.59 Evaluation is required. If the answers in III.3.b are ALL NO describe the basis for the conclusion (attach additional discussion as necessary):
Part IV - 10 CFR 50.59 SCREENING CONCLUSION (Resource Manual 5.3.4).
Check all that apply:
A 10 CFR 50.59 Evaluation is E] required or Z NOT required.
A Point Beach FSAR change is [] required or Z NOT required. If an FSAR change is required, then initiate an FSAR Change Request (FCR) per NP 5.2.6.
A Regulatory Commitment (CLB Commitment Database) change is El required or Z NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.
is A Technical Specification Bases change is [] required or Z NOT required. If a change to the Technical Specification Bases required, then initiate a Technical Specification Bases change per NP 5.2.15.
A Technical Requirements Manual change is E] required or Z 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 -----
the NOTE: NEI 96-07. Appendix B. Guidelines for 10 CFR 72.48 Implementation should be used for guidance to determine proper responses for 72.48 screenings.
PART V (72.48) - 10 CFR 72.48 INITIAL SCREENING QUESTIONS activity.
Part V determines if a full 10 CFR 72.48 screening is required to be completed (Parts VI and VII) for the proposed YES NO QUESTION El [] 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 follovs: Multi-Assembly Sealed Basket (MSB), MSB Transfer Cask (MTC), MTC Lifting Yoke, Ventilated Concrete Cask (VCC), Ventilated Storage Cask (VSC), VSC Transporter (VCST), ISFSI Storage Pad Facility, ISFSI Storage Pad Data/Communication Links, or PPCS/ISFSI Continuous Temperature Monitoring System?
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR numberon all pages Page 5 El El Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System?
El [] Does the proposed activity involve IN ANY MANNER SSC(s) needed for plant operation which are also used to support cask loading/unloading activities, as follows: Spent Fuel Pool (SFP), SFP Cooling and Filtration (SF),
Primary Auxiliary Building Ventilation System (VNPAB), Drumming Area Ventilation System (VNDRM),
RE-105 (SFP Low Range Monitor), RE-135 (SFP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bridge, Truck Access Area, or Decon Area?
El [] Does the proposed activity involve a change to Point Beach CLB design criteria for external events such as earthquakes, tornadoes, high winds, flooding, etc.?
El [] Does the activity involve plant heavy load requirements or procedures for areas of the plant used to support cask loading/unloading activities?
El [] 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 [E NOT APPLICABLE.)
compare the proposed activity to the relevant portions of the ISFSI licensing basis and answer the following questions:
YES NO QUESTION El [] Does the proposed activity involve caskflSFSI Safety Analyses or plant/cask/ISFSI structures, systems and components (SSCs) credited in the Safety Analyses?
E] Z Does the proposed activity involve plant, cask or ISFSI SSCs that support SSC(s) credited in the Safety Analyses?
El [ Does the proposed activity involve plant, cask or ISFSI SSCs whose function is relied upon for prevention of a radioactive release, OR whose failure could impact SSC(s) credited in the Safety Analyses?
E] Z Does the proposed activity involve cask/ISFSI described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, CoC conditions, or orders?
El [] Does the activity involve a method of evaluation described in the ISFSI licensing basis?
E] Z Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
El Z Does the activity exceed or potentially affect a cask design basis limitfor afission product 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 Parts VII as not applicable, and document the 10 CFR 72.48 screening in the conclusion section (Part VIII).
If any of the above questions are marked YES, identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.
.'ART VII (72.48) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (NEI 96-07, Appendix B, Section B.4.2.1)
(If ALL the questions in Part V or Part VI are answered NO, then Part VII is Z NOT APPLICABLE.)
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.590h2.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 6 Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 72.48 Evaluation is required; EXCEPT where noted in Part VII.3.
VII. I Changes to the Facility or Procedures YES NO QUESTION El [I Does the activity adversely affect the designfunction of a plant, cask, or ISFSI SSC credited in safety analyses?
El El Does the activity adversely affect the method of performing or controlling the designfunction of a plant, cask, or ISFSI SSC credited in the safety analyses?
If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion, as necessary):
VII.2 Changes to a Method of Evaluation (If the activity does not involve a method of evaluation, these questions are El NOT APPLICABLE.)
YES NO QUESTION El El Does the activity use a revised or different method of evaluation for performing safety analyses than that described in a cask SAR?
El El Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in a cask SAR?
If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO, describe the basis for the conclusion (attach additional discussion, as necessary):
VII.3 Tests or Experiments (If the activity is not a test or experiment, the questions in VII.3.a and VH.3.b are E] NOT APPLICABLE.)
- a. Answer these two questions first:
YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis?
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 VII.3.b. If the answer to EITHER question is YES, then briefly describe the basis.
- b. Answer these additional questions ONLY for tests or experiments which do not meet the criteria given in VII.3.a above.
If the answer to either question in VII.3.a is YES, then these three questions are [E NOT APPLICABLE:
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 7 YES NO QUESTION El El Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in the ISFSI licensing basis?
E] F1 Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descriptions in the ISFSI licensing basis?
El El Does the activity place the cask or ISFSI facility in a condition not previously evaluated or that could affect the capability of a plant, cask, or ISFSI SSC to perform its intended functions?
If any answer in VII.3.b is YES, a 10 CFR 72.48 Evaluation is required. If the answers are all NO, describe the basis for the conclusion (attach additional discussion as necessary):
PART VIII - DOCUMENT TIlE CONCLUSION OF THE 10 CFR 72.48 SCREENING Check all that apply:
A 10 CFR 72.48 Evaluation is E] required or Z NOT required. Obtain a screening number and provide the original to Records Management regardless of the conclusion of the 50.59 or 72.48 screening.
A VSC-24 cask Safety Analysis Report change is [] required or Z NOT required. If a VSC-24 cask SAR change is required, then contact the Point Beach Dry Fuel Storage group supervisor.
A Regulatory Commitment (CLB Commitment Database) change is E] required or Z NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.
A change to the VSC-24 10 CFR 72.212 Site Evaluation Report is E] required or Z NOT required. If a VSC-24 10 CFR 72.212 Site Evaluation Report change is required, then contact the Point Beach Dry Fuel Storage group supervisor.
POINT BEACH NUCLEAR PLANT AOP-23 UNIT 1 ABNORMAL OPERATING PROCEDURES MAJOR Revision 0 6/9/99 ESTABLISHING ALTERNATE AFW SUCTION SUPPLY Page 1 of 5 A. PURPOSE
- 1. This procedure provides directions to establish an alternate source of water to the suction of the AFW pumps.
B. SYMPTOMS OR ENTRY CONDITIONS
- 1. This procedure is entered whenever CST level is less than 8 Feet and AFW flow is required to maintain a secondary heat sink.
C. REFERENCES
- 1. None rf),TT)T77TTTCTT TTqTP
FOLDOUT PAGE FOR AOP-23 UNIT 1
- 1. AFW MINIMUM FLOW REQUIREMENTS Monitor and maintain minimum AFW discharge flow or stop the affected AFW pump as necessary to control S/G levels.
o P-38A minimum flow - GREATER THAN 50 GPM o P-38B minimum flow - GREATER THAN 50 GPM rj o P-29 minimum flow - GREATER THAN 75 GPM ,
'3
POINT BEACH NUCLEAR PLANT AOP-23 UNIT 1 ABNORMAL OPERATING PROCEDURES MAJOR Revision 0 6/9/99 ESTABLISHING ALTERNATE AFW SUCTION SUPPLY Page 2 of 5 IF AFW pump Low Suction Pressure trip is actuated. THEN align service water to AFW pumps:
- 1) Open service water to AFW pump suction valve.
IAF-4006
- 2) Open Low Suction/Overspeed Trip Valve from Control Room:
a) Place 1MS-2082. 1P-29 Low Suction/Overspeed Trip Valve Reset Op~rator to "CLOSE" b) Check IMS-2082. IP-29 Low Suction/Overspeed Trip Valve Reset Operator - CLOSED c) Place 1MS-2082. 1P-29 Low Suction/Overspeed Trip Valve Reset Operator. to "OPEN" d) Check 1MS-2082. IP-29 Low Suction/Overspeed Trip Valve Reset "Operator - OPEN
- b. IF P-38A. train A motor-driven AFW pump is desired. THEN perform the following:
- 1) Open service water to AFW pump suction valve.
AF-4009
- 2) Place motor-driven AFW pump control switch to "PULL-OUT" and then to "START" position and release.
C. IF P-38B. train B motor-driven AFW pump is desired. THEN perform the following:
- 1) Open service water to AFW pump suction valve.
@ AF-4016
- 2) Place motor-driven AFW pump control switch to "PULL-OUT" and then to "START" position and release.
FOLDOUT PAGE FOR AOP-23 UNIT 1
- 1. AFW MINIMUM FLOW REQUIREMENTS Monitor and maintain minimum AFW discharge flow or stop the affected AFW pump as necessary to control SIG levels.
o P-38A minimum flow - GREATER THAN 50 GPM o P-38B minimum flow - GREATER THAN 50 GPM o P-29 minimum flow - GREATER THAN 75 GPM (N
C
POINT BEACH NUCLEAR PLANT AOP-23 UNIT 1 ABNORMAL OPERATING PROCEDURES MAJOR Revision 0 6/9/99 ESTABLISHING ALTERNATE AFW SUCTION SUPPLY Page 3 of 5 CAUTION The following valve lineup will isolate all makeup to Unit 2 hotwell from the condensate storage tank.
2 Isolate condensate storage tank from Unit 2:
- a. Shut Unit 2 condenser low flow make-up inlet isolation valve.
- b. Ensure Unit 2 condenser high flow make-up inlet isolation valve SHUT e 2CS-94
- c. Ensure Unit 2 manual condenser makeup valve - SHUT
- d. Direct Unit 2 operator to shut both steam generator blowdown isolation valves.
a 2MS-5959. train A
- 2MS-5958. train B.
- e. Direct Unit 2 operator to shut both steam generator sample isolation valves.
"*2MS-2083. train A
"*2MS-2084. train B
FOLDOUT PAGE FOR AOP-23 UNIT I r4
- 1. AFW MINIMUM FLOW REQUIREMENTS Monitor and maintain minimum AFW discharge flow or stop the affected ANW pump as necessary to control SIG levels.
o P-38A minimum flow - GREATER THAN 50 GPM o P-38B minimum flow - GREATER THAN 50 GPM
- o P-29 minimum flow - GREATER THAN 75 GPM
POINT BEACH NUCLEAR PLANT AOP-23 UNIT 1 ABNORMAL OPERATING PROCEDURES MAJOR ESTABLISHING ALTERNATE AFW SUCTION SUPPLY Revision 0 6/9/99 Page 4 of 5 3 Align service water to all running AFW pumps:
- a. IF IP-29 turbine-driven AFW pump is running. THEN align service water to 1P-29:
- 1) Ensure service water to AFW pump suction valve - OPEN lAF-4006 1
- 2) Locally shut manual CST suction valve.
IlAF-26
- b. IF P-38A train A motor-driven AFW pump is running. THEN align service water to P-38A:
- 1) Ensure service water to AFW pump suction valve OPEN e AF-4009
- 2) Locally shut manual CST suction valve.
- AF-39
- c. IF P-38B train B motor-driven AFW pump is running. THEN align service water to P-38B:
- 1) Ensuire service water to AFW pump suction valve - OPEN a AF-4016
- 2) Locally shut manual CST suction valve.
- AF-52
FOLDOUT PAGE FOR AOP-23 UNIT 1 I. AFW MINIMUM FLOW REQUIREMENTS N Monitor and maintain minimum AFW discharge flow or stop the affected AFW pump as necessary to control S/G levels.
"o P-38A minimum flow - GREATER THAN 50 GPM "o P-38B minimum flow - GREATER THAN 50 GPM "o P-29 minimum flow - GREATER THAN 75 GPM C
POINT BEACH NUCLEAR PLANT AOP-23 UNIT 1 ABNORMAL OPERATING PROCEDURES MAJOR Revision 0 6/9/99 ESTABLISHING ALTERNATE AFW SUCTION SUPPLY Page 5 of 5 4 IF service water can NOT be provided as an alternate AFW supply, THEN establish fire water to--both condensate storage tanks:
- a. Establish flow to "A" condensate storage tank:
- 1) Unreel two hoses to "A" CST spare connections at AF-4.
"*HR-11. hose reel near maintenance shop door No.20 on 26' level
" ER-14, hose reel near Unit 1 halon bank on 26' level
- 2) Ensure "A" CST inlet spare connection valve - SHUT
- AF-4
- 3) Remove caps and couple hoses to connectors.
- 4) Open "A" CST inlet spare connection valve.
- AF-4
- 5) Open hose reel isolation valves.
"*FP-66 for hose reel BR-li
"* FP-72 for hose reel BR-14
- b. Establish flow to "B" condensate storage tank:
- 1) Unreel two hoses to CST spare connections at AF-7.
"*BR-40, hose reel near cable spreading room door No.28 on 26' level
" HR-41. hose reel near cable spreading room door No.27 on 26' level
- 2) Ensure "B" CST inlet spare connection valve -'SHUT o AF-7
- 3) Remove caps and couple hoses to connectors.
- 4) Open "B" CST inlet spare connection valve.
- AF-7
- 5) Open hose reel isolation valves.
- FP-251 for hose reel BR-40
- -FP-247 for hose reel ER-41
-END-
FOLDOUT PAGE FOR AOP-23 UNIT 1 P4
- 1. AFW MINIMUM FLOW REQUIREMENTS Monitor and maintain minimum ANW discharge flow or stop the affected ANW pump as necessary to control S/G levels.
o P-38A minimum flow - GREATER THAN 50 GPM o P-38B minimum flow - GREATER THAN 50"GPM o P-29 minimum flow - GREATER THAN 75 GPM C