ML030870757

Document Review & Approval, PBF-1584, Design Input Checklist

ML030870757
Person / Time
Site:	Point Beach
Issue date:	08/15/2002
From:	Mark Miller, Rosseau M Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0094 PBF-1584 Rev 10
Download: ML030870757 (17)

Text

Nuclear Power Business Unit DOCUMENT REVIEW AND APPROVAL Note: Refer to NP 1.l.3for requireme) Page I of I - INITIATION Doc Number PBF-1584 Unit PBO Usage Level NA Proposed Rev No 10 Title DESIGN INPUT CHECKLIST CI1assificcation NA

[ Revision El Cancellation El New Document El Other (e g periodic review, admin hold)

List Temporary Changes/Feedbacks Incorporated: N/A Description of Alteration/Reason (if necessary, continue description of changes on PBF.0026c and attach.)

See attached PBF-0026c List other documents required to be effective concurrently with the revision (e g , other procedures, forms, drawings, etc.):

None Document Preparer (print/sign) Michael Rosseau /'1I ) Z d..o- Date 08/'12/2002 Indicates draft prepared according toNPI.1.3, any commitments/bases changes have been documented and resolved.

II - TECHNICAL REVIEW (Cannot be the Preparer or Approval Authority) .,

Technical Reviewer (print/sign) Michael L. Miller / j Z( Date"_____ 2. _

Indicates draft technically correct, consistent with references/bases/upper tier requirements, requirements of NP 1.1.3 completed ITT- DOCUMENT OWNER REVIEW --

Required Reviewers/Organizations: N/A Validation Required? ED NO El YES El WAIVED (Group Head Approval and Reason Required)

Reason Validation Waived: N/A Continue on PBF-0026c if necessary.

Validation Waiver Approval:

Group Head Signature Changes pre-screened according to NP 5.1.8? [- NO ER YES (Provide documentation according toNP 5.1.8)

Screening completed according to NP 5.1.8? Z NA El YES (Attach copy) Safety evaluation required? [ NO El YES Training or briefing required? [ NO El YES If YES, training or briefing required before issue? El NO El YES Training assistance desired? [ NO El YES If YES, Training Coordinator contacted/date: /

[ QR/MSS Review NOT Required (Admin or NNSR only) [] QR Review Required E] MSS Review Required (reference NP 1.6 5)

Document Owner (print/sign) Michael Rosseau /or -, 5 F._ Date *, 1 Indicates document is technically correct, can be performed as wntten, does not adversely affect personnel or nuclear safety, appropriate re iews have been performed (i.e, technical, cross-disciplinary, validation and 50.59/72.48), comments have been resolved and incorporated as appropriate, affected documents/training/briefing have been identified and word processing completed. Document Control notified if emergent issuance required (e g , may be less than 2 days for procedure issuance)

IV - APPROVAL (The Preparer, Qualified Reviewer (QR), and Approval Authority shall be different individuals)

QR/MSS (print/sign) N/A / Date Indicates 50.59/72 48 applicability assessed, any necessary screenings/evaluations performed, determination made as to whether additional cross disciplinary review required, and if required, performed MSS Meeting No. N/A Approval Authority (print/sign) Date k"-,

V- RELEASE FOR DISTRIBUTION 6

'Z NA E] YES Pre-implementation requirements complete (e.g, training/briefings, affected documents, word es etc.).

Z Specific effective date not required. Issue per Document Control schedule.

[] Required effective date: (Coordinate date with Document Control)

Document Owner/Designee (print/sign) Michael Rosseau Date Effective Date (to be entered by Document Control) AUG I q 71111 i1i'l *-,,

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Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page __ ofP, Doc Number PBF-1584 Revision 10 Unit PBO Title DESIGN INPUT CHECKLIST Temporary Change Number N/A Description of Changes:

Step

• Change/Reason A.6 Add "(Contact EPIX coordinator)". Editorial A. 10 Delete "Failure analysis is only required for maintenance rule sytems." This gets addressed for all mods.

A. I0.b Add "(Consider both equipment and human induced failures)". Reference CA003703.

A. 11.a & b Combine questions for efficiency.

C. 17 Delete reference to DG-E06 which has been cancelled and add "Contact EDA group for guidance".

F.5.e & f Change Rem to rem. Editorial.

End of F.5 Delete NP 4.2.3 ALARA Review Procedure and add NP 42.1 Plant ALRARA Program. Editorial.

F.6.d Add "control room habitability" and reference OE 11400, RG 1.78 and NP 3.1.6. Reference CA001796.

G.13 Add a new question "Require that equipment be grounded?" Reference OE 12765.

t I

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Other Comments

' Note: Recording of Step Number(s) is not required for multiple occurrences of identical information or %%hennot beneficial to reviewers

Point Beach Nuclear Plant 10 CFR 50.59/72.48 APPLICABILITY FORM Page I Pa 2 e I BriefActivity Title Revise PBF-1584 Design Input Checklist.

or

Description:

This form is required to be completed and attached to the applicable activity change forms to document all or portions of an activity that are covered by another regulation other than 10 CFR 50.59 and 10 CFR 72.48 (pre-screening criteria 2). See NP 5.1.8, 10 CFR 50.59/72.48 Applicability, Screening and Evaluation (New Rule).

NOTE: Guidance for searching the FSAR, Technical Specifications, Regulatory Commitments (CLB Commitment Database) and other licensing basis documents can be found in NP 5.1.8, Attachment G.

NOTE: Although 10 CFR 50.59 and 72.48 may not be applicable to the processes listed below, change activities conducted under these processes may require changes to the FSAR. If so, initiate FSAR changes per NP 5.2.6, FSAR Revisions.

Regulatory or Plant Process YES NO

1. Does the activity require a change to the Facility Operating License, License Conditions or Technical Specifications? (If the answer is YES, process the applicable changes per NP 5.2.7, License Amendment Request Preparation, Review and Approval.)

2. NOTE: The Quality Assurance Plan is described in FSAR Section 1.4.

Does the activity require a change to the Quality Assurance Program? If the answer is El 10 YES, process the applicable changes per NP 11.1.3, QA Program Revisions.

3. NOTE: Implementation of Security Plan changes that require physical changes to the plant, or changes to operator access to the plant require a screening.

NOTE: Security is described in FSAR Section 12.7.

Does the activity require a change to the PBNP Security Plan, a safeguards contingency LI plan, or security training and qualification plan? If the answer is YES, assess the acceptability of the change per 10 CFR 50.54(p) using Security procedures.

4. NOTE: The Emergency Plan is described in FSAR Section 12.6.

Does the activity require a change to the Emergency Plan? If the answer is YES, process the applicable changes per NP 1.8.1, Emergency Preparedness Procedures.

5. NOTE: The Radiation Protection Program is described in FSAR Section 11.4.

Does the activity require a-change to the PBNP Radiation Protection Program described in NP 4.2.9, Radiation Protection, OR is the activity within the scope of NP 4.2.9 and 10 CFR 20, Standards for Protection Against Radiation?

6. NOTE: Changes to the plant or method of evaluation that result in re-analysis of the FSAR loss-of-coolant accident (LOCA) analysis require a screening.

Does the activity require a change to the FSAR LOCA analysis results subject to 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors? If the answer is YES, process the applicable changes per NP 5.2.12, 10 CFR 50.46 Reporting Requirements, and NP 5.2.6 FSAR Revisions.

7. NOTE: Regulatory commitments are found in the CLB Commitment Database.

Does the activity involve a change to a Regulatory Commitment ? If the answer is YES, 0 process the applicable changes per NP 5.1.7, Regulatory Commitment Changes.

8. Does the activity involve a change to the Environmental Manual (EM), Radiological Effluent Control Program Manual (RECM), Offsite Dose Calculation Manual (ODCMvl),

or Process Control Program (PCP), AND does NOT involve changes in use of explosive El z gases in waste treatment systems? If the answer is YES, document the applicable changes per the requirements of TS 15.7.8.7.B {ITS 5.5.1}.

Point Beach Nuclear Plant 10 CFR 50.59/72.48 APPLICABILITY FORM Pno* 9 Regulatory or Plant Process YES NO NOTE: For purposes of determining 10 CFR 50.59/72.48 applicability, the determination of an administrative procedure below takes precedence over definitions or classifications in other plant procedures or guidelines.

9. Does the activity require a change to an administrative procedure or controlled document ONLY?

ALL of the following statements shall be true for the procedure or controlled document to be considered administrative.

a. DOES NOT direct how plant structures, systems, or components are operated, maintained, tested or repaired either specifically OR generically.

b. DOES NOT specify acceptance criteria or operating limits for plant structures, systems, or components.

c. DOES NOT specify parts, materials, chemicals, lubricants, etc. to be used in plant structures, systems, or components.

d. DOES NOT specify compensatory action(s) to address plant structures, systems, or components out of service, or to address non-conforming conditions.

e. DOES NOT affect operator access to operating areas of the plant.

10 CFR 50.59/72.48 APPLICABILITY CONCLUSION NOTE: If ANY portion of the activity is NOT controlled by one or more of the processes above, further 10 CFR 50.59 / 72.48 review is required (i.e., portions not covered by the above processes shall be prescreened to other criteria or screened).

ALL aspects of the activity are controlled by one or more of the processes above, therefore NO YES NO additional 10 CFR 50.59 and 72.48 review is required.

0 El If the above question is answered NO briefly describe the portions of the activity NOT covered by one or more of the above processes:

N/A Performed By Michael Rosseau / "__--,J___ . Date 08/12/2002 Name (Print) Signature Reviewed By Michael L Miller I *'. /. Date iz/

Name (Print) Signature

Point Beach Nuclear Plant DESIGN INPUT CHECKLIST fication or Temporary Modification Number:

Title:

INSTRUCTIONS: Consider the basic functions of each structure, system, and component, (SSC), when answering the questions. The designer shall check the appropriate box for each design input or section. All inputs that apply to the design shall be explained. The explanation may be documented on this checklist or in the design summary. The reviewer shall review the checklist, and any differences between the designer and the reviewer should be addressed. This checklist addresses most design concerns, but is not all encompassing. Any additional concerns should be addressed in the design summary.

(Updates to this form covered by SCR 97-411.)

APPLIES TO DESIGN YES NO A. General codes, standards, regulatory requirements, and design criteria.

1. Are any of the PBNP FSAR general design criteria applicable? (Reference FSAR, Section 1.3.

Identify and address design criteria as appropriate.)

2. Are any design requirements contained in commitments affected? (Reference CLB database and the Safety Evaluation/Screening associated with this change.)

3. Meet State of Wisconsin Administrative Code requirements? (Refer to ILHR 41.42, PSC 114, and El El other sections as appropriate for requirements.)

4. Meet existing DNR permits or require DNR approval? (Contact WE Environmental Department.) El El

5. Consider the effect of design and accident conditions, such as pressure, temperature, fluid chemistry, and radiation on components, including internal elastomers and material coating compatibility. El El (Changes in design parameters may impact Environmental Qualification.)

6. Incorporate new types/models of equipment not presently used at PBNP? (Contact EPIX coordinator.) El El

7. Affect accessibility of any equipment? Consider interim conditions, future maintenance, and in-service El El inspection. (Reference CIMs and drawings for manufacturer's clearance requirements.)

8. Require breaching a High Energy Line Break (HELB) barrier? (Reference NP 8.4.16) If yes, EQ 5 El engineer review required.

9. Consider operating experience from PBNP and industry events. (Reference DG-G04 for operating experience reviews and NPRDS, NODIL, CHAMPS, INPO Keywords, or other databases.)

APPLIES TO DESIGN DESIGN INPUT CHECKLIST NO YES

10. Consider failure effects on structures, systems, and components: (Contact the NSA-PSA group for guidance and scope).

El

a. The design discusses those events/accidents which the system/components are to withstand? El

b. The failure effect of the system/components: (Reference the NSA-PSA Group, Operating Experience, & IEEE-352-1975.)

El

• How components may fail, and the effect of the failure on the system and related systems?

• What mechanisms might produce failures? (Consider both equipment and human induced failures.)

• How a failure would be detected?

• What provisions are included to compensate for the failure?

11. Does the design add or remove components in containment?

a. Change the amount of exposed aluminum or zinc in containment? (Reference DG-G07 and FSAR Section 5.6.)

b. Introduce materials into containment that could affect sump performance or lead to equipment degradation? (Reference DG-G07.) El

c. Decrease free volume of containment? El

d. Require addition or modification of a containment penetration boundary? (Consult the El containment system engineer.)

El El El

e. Require painting in containment? (Reference MI 36.3.)

El

12. Consider potential for fuel failure?

El

a. Affect fuel handling equipment?

El

b. Present the potential for introducing foreign material/debris into the RCS or connected systems? El El

c. Affect core barrel flow patterns? ("Baffle jetting" concerns)

13. Meet requirements to abandon equipment if applicable. (Reference NP 7.1.5)

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APPLIES TO DESIGN DESIGN INPUT CHECKLIST YES l~l..O 4echanical requirements. (Contact Mechanical Design Engineering for guidance.)

1. Have applicable ASME Boiler & Pressure Vessel codes or other standards been identified?

(Reference the applicable specification. In addition, safety-related components should be reconciled jJ El with DG-M16, and QA components should be reconciled with ANSI N45.2.)

2. Affect or add components/systems to ASME Section XI class 1, 2. or 3 equipment? (Reference PBNP CHAMPS, CBD drawings, and IST Coordinator. If YES, follow NP 7.2.5, Repair/Replacement El El Program.)

3. Require State of Wisconsin Administrative Code permits/approvals? (Reference NP 7.4.9, Wisconsin El Administrative Code for Boilers and Pressure Vessels or the Authorized Inspector.)

4. Consider component performance requirements such as capacity, rating, output? Q 5

5. Consider hydraulic requirements such as pump net positive suction heads, allowable pressure drops, El El allowable fluid velocities and pressures, valve trim requirements, packing/seal requirements?

6. Provide vents, drains, and sample points to accommodate operational, maintenance and testing needs? El El

1. Require service water? (Both essential and nonessential service water loads are modeled, and load El El changes must be evaluated. Contact the SWAP Coordinator.)

8. Require the addition of check valves? (Reference DG-M13 for selection guidance.) El El

9. Require and evaluate any additional loading on instrument or service air, circ, fire protection, or El El demineralized water, or other system?

10. Evaluate any additional loading on HVAC systems or affect ventilation flow during or after installation? (This will require an EQ review for potential updates to EQSS, EQML & EQMR.)

11. Affect ventilation barriers, including containment, primary auxiliary building, or control room? El El

12. Require insulation? (Reference WE specification PB-485 for insulation, and NP 1.9.10 for asbestos El El control.)

13. Require lubrication? (Reference Lubrication Manual.) El El nor I - I

APPLIES TO DESIGN DESIGN INPUT CHECKLIST YES No

14. Require an independent means of pressure relief? (Reference B31.1.)

15. -Affect the assigned system design pressure or temperature? El El

16. Involve cobalt-laden materials into the RCS or into systems that supply the RCS? (Reference NP 4.2.29, "Source Term Reduction Program.")

El 1:1

17. Are new materials and their coatings/plating compatible with system chemistry and disposal systems (NP 8.4.15)?

El El

18. Affect embedded or buried piping?

C. Electrical requirements. (Contact Electrical Design Engineering for guidance.) El El

1. Consider design conditions such as ampacity, voltage drop?

2. Consider component and system performance requirements, such as current, voltage, or power? El "Considerredundancy, diversity and separation requirements of structures, systems and components?

(Reference DG-E07 for separation of electrical circuits.) El

4. Comply with protective relaying requirements of equipment and systems? El El

5. Selection of overcurrent devices for proper protection and coordination? (Reference DG-E04 for E]

El El El selection of molded case circuit breakers.)

El El

6. Affect available fault current at any bus? El El El

7. Assure that all added cables meet fire retardancy requirements? (Reference FPER Section 4.1.8, El

[]

IEEE 383.)

El El 1:1

8. Be compatible with existing electrical insulation and wiring? El

9. Affect ampacity of existing cables?

"). Maintain UL (or equivalent) listings?

APPLIES TO DESIGN DESIGN INPUT CHECKLIST YES _qO

11. Alter the voltage harmonic distortion content or change the non-linear loading (i.e., the addition of switching power supplies, the alteration of the circuit's power factor, etc.) on a vital or sensitive El 11 instrument bus?

12. Add new raceways? (Reference DG-E03 for electrical raceway sizing and DG-E02.) El El

13. Add cables to existing electrical raceways? El El

14. Be routed through fire wrapped raceways? El El

15. Affect the station grounding or lightning protection system? El El

16. Make any vital circuit susceptible to ground? El El

17. Affect emergency diesel loading? (Contact Electrical Design Analysis group for guidance.) El El

18. Add more station battery loading? El El

19. Add load to a vital bus? El El

20. Add load to a non-vital bus? El El

21. Be compatible with service transformer capacity? El El

22. Consider electromagnetic interference between new/existing equipment and electromagnetic coupling El El interactions between circuits?

23. Affect embedded conduits or buried cables, including the station grounding system? El El PRC I 96 in. 2 in any wall, ceiling, or other barrier? El El

b. Require work within 20' of fence? El El

c. Affect security equipment and documents, including those containing safeguards information?

El El (Contact Security for design development requirements and design concurrence.)

d. Affect access controls? Fl El

13. Safety requirements:

a. Affect safety equipment and thereby create personnel hazards (i e., removal of handrails)? El

b. Introduce hazardous material into the plant? (Reference NP 1.9.1 ) 0l 1- r-

a.

APPLIES TO DESIGN DESIGN INPUT CHECKLIST YES &O C. Affect evacuation routes or escape provisions from enclosures?

d. Meet OSHA regulations? (Reference Wisc. Electric Safety Manual and OSHA 29 CFR 1910.)

El E]

e. Move any energy sources? If yes, verify installation document covers move, including transferring danger tags.

El 0: El El

f. Require that equipment be grounded?

Designed by: Date:

Reviewed by: Date:

PRR.I 4,Ra