ML18052B003
| ML18052B003 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/08/1987 |
| From: | Kuemin J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-83-28, NUDOCS 8705120340 | |
| Download: ML18052B003 (23) | |
Text
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'i consumers Power POWERINli MICHlliAN"S PROliRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 May 8, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
ADDITIONAL INFORMATION - VENDOR INTERFACE AND EQUIPMENT CLASSIFICATION - GENERIC LETTER 83-28 Nuclear Regulatory Commission letter dated March 9, 1987 transmitted a Request for Additional Information concerning Items 2.1 and 2.2 of Generic Letter 83-28; "Vendor Interface (Reactor Trip System Components) and Equipment Classification (Programs for all Safety Related Components)."
The responses to that request are provided below.
Request:
A.
Item 2.1 (Part 2) "Vendor Interface (Reactor Trip System Components)"
Our review of the licensee's submittals indicates that the licensee has identified an interface with their nuclear steam supply system vendor.
However we are unable to determine that the licensee's vendor interface program encompasses a periodic and continuing feedback mechanism.
Item 2.1 (Part 2) states that the vendor interface program shall include *periodic communication with vendors to assure that all app'iicable information has been received.
The licensee needs to reference the C-E "Infobulletins" program and note that return receipts are required for the bulletins or otherwise describe their feedback program for assuring that all relevant material is received.
Response
To disseminate information relevant to its supplied plants, Combustion Engineering (C-E) maint~ins its Availability Data Program (ADP).
One of the outputs from this program is the series of ADP "Infobulletins" which provide one vehicle for C-E to notify its plants of potentially significant issues.
The Operating Experience Review Coordinator for Palisades receives Infobulletins directly from C-E.
As the program requires, a receipt is provided to C-E for each Infobulletin as verification that the information has been received.
OC0587-0057-NL04 8705120340 870508 5 PDR. ADOCK 0500~B~
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.t Nuclear Reactor Regulatory Palisades Plant GL 83 Add'l Information May 8, 1987 Each Infobulletin is formally evaluated and tracked by the Operating
.Experience Review Program.
Since each Infobulletin is sequentially numbered, it is readily apparent if one has not been received.
In addition, C-E issue~
a quarterly ADP report which discusses issues* potentially relevant to C-E plants.
These include Infobulletin summaries as well as discussions of other issues.
Finally, C-E periodically transmits lists of Infobulletins issued to date.
These lists are used as a final verification that all Infobulletins have been incorporated into the Operating Experience Review Program.
Request:
B.
Item 2.2 (Part 1) "Equipment Classification (Programs For All Safety-Related Components)"
Item 2.2.1 - Program 2
The licensees' responses do not confirm that all safety-related components are designated as safety-related on plant documents such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handling systems so that personnel performing activities that affect such safety-related components are aware that they are working on safety-related components and are guided by safety-related procedures and constraints.
The licensee needs to state that their equipment classification conforms with the above staff position.
If all safety-related components are not designated as safety-related on the relevant documents, the licensee should specifically describe the exceptions and provide a justification for such exceptions for staff review.
Response
The Palisades "Q-List" administrative procedure (AP 9.30) provides the guidelines utilized *by plant personnel to determine the safety-related classification of structures, systems, components and activities in accordance with the requirements established by the Consumers Power Quality Assurance Program.
Guidelines for safety-related classification of consumable materials is provided in administrative procedure "Consumables Control" (AP 4. 27).
These safety-related determinations are documented in the "Q-List" procedure for systems and structures, in the Equipment Data Base (computer based information system) for plant components, and in the "Consumables Control Program Manual'~ for consumables and chemicals.
The Q-List determinations are utilized by plant personnel to determine the "Q" status (Q = Safety Related, Non-Q = Non-Safety Related) of plant working documents such as procedures, work orders, tests, procurement documents, and modifications.
Examples of the source information is presented in Attachments 1 through 4 as follows:
OC0587-0057-NL04
Nuclear Reactor Regulatory Palisades Plant GL 83 Add'l Information May 8, 1987 Attachment Attachment Attachment Attachment 1 - Structures 2 - Systems 3 -
Components 4 - Consumables
- From Admin 9.30 "Q-List" Procedure
- From Admin 9.30 "Q-List" Procedure
- From Equipment Data Base*
- From "Consumables Control Program Manual" 3
- Note:
If a plant component is not on the Equipment Data Base, it is required by the "Q-List" Administrative Procedure to be treated as Q-Listed until a determination has been performed, approved and entered into the Equipment Data Base.
The assignment of "Q" or "Non-Q" is designated on plant working documents as shown on Attachment 5 through 8 as follows: - Work Order - Procurement Documents - Procedure/Test Cover Sheet - Modification Documents Plant drawings, such as P&ID's, electrical schemes and vendor prints, are not specifically designated as "Q" or "Non-Q"; however they are considered to complement the work implementing documents shown in Attachment 5 through 8.
The work implementing documents provide the control functions required to identify an activity as "Q" or "Non-Q."
The plant "Q-List" program controls the designation of components and activities as safety or non-safety related to ensure that appropriated levels of the Quality Assurance Program to meet 10CFR50 Appendix B are applied to an activity.
This along with the designation on working level documents insur.es that maintenance, procurement, modification, and test activities on safety-related systems, structures, and components are completed in accordance with these requirements.
The safety-related designation on the worki~g level documents also ensures that personnel performing activities are aware that the activities are safety-related.
/.r
~uemin Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachments OC0587-0057-NL04
OC0587-0057-NL04 ATTACHMENTS Consumers Power Company Palisades Plant Docket 50-255 SELECTED EXAMPLES OF SAFETY-RELATED COMPONENT PROGRAM CONTROLS May 8, 1987 18 Pages
STRUCTURES The
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P~..lof_I Proc No 9.30 Appendix A Revision 4 Page 1 of 2
- 1.
Containment Building including all structural portions of the building and those items needed to maintain the integrity of the structure.
This does not include roofing, siding or other architectural items.
- 2.
Auxiliary Building including all structural portions of the building and those items needed to maintain the integrity of the structure.
This does not include roofing, siding or other architectural items.
- 3.
Auxiliary feed pump room.
- 4.
Containment south electrical penetration area.
- 5.
Intake structure.
- 6.
Spent fuel storage pool an~ fuel racks including~ll structural portions of the building and those items needed to maintain the integrity of the structure.
This does not include roofing, siding or other architectural items *
- 7.
Those portions of structures whose continued function is not required but whose failure could reduce the functioning of any Plant Q-Listed struc-ture, system, or component to an unacceptable safety level or could result in an incapacitating injury to occupants of the control room.
- 8.
Those portions of structures that form interfaces between Seismic Category I and non-Seismic Category I features.
The following structures are not Q-listed nd work may be performed on these buildings and items in these bu1 ithout first having a Q interpre-tation, as non-Q:
- 9.
Service Building.
- 10.
Support Building.
- 11. _New Warehouse.
- 12.
Switchyard Relay House.
- 13.
PE&C Building
- ad0782-0795f-93-154
Q-LISTED SYSTEMS p~~\\1IM:~o: N~9.JO Appendix B Revision 4 Page 1 of 4
~~-t'-e~ *R.-el~A-c4 piping, instrumentation, etc, as
- 1.
BAG - Building and Grounds (Refer to Appendix A for a iisting of Q structures.)
Auxiliary building elevator and associated mechanical and electrical components are not Q-Listed.
- 2.
CAS - Instrument and ~ervice Air
- 3.
CCS - Component Cooling
- 4.
- s.
- 6.
- 7.
CDS Condensate and Condenser CHM - Chemical Addition CIS - Containment Isolation System Containment isolation system is entirely Q-Listed and is defined to include all components which are required to o~erate to ensure containment isolation.
This includes the electrical/mechanical penetrations and piping and test valves.
CLP - Containment Building and Crane The containment building is defined in Appendix A as Q-Listed.
The containment building crane's structural components, cables, hooks, sheaves and brakes are also Q-Listed.
This applies to both the main and auxiliary components.
The containment building crane's structural components *** brakes and load bearing devices that are attached to the crane to lift Q-Listed components are also Q-Listed.
- 8.
CRD - Control Rod Drive
- 9.
All mechanical portions of the control rod drive, up to and including the clutch, are Q-Listed.
The remaining mechanical and all of the electrical components and associated circuitry are excluded from xhis list.
CRS - Containment Air Cooliog
- 10.
CVC - Chemical and Volume Control
- 11.
DHW - Demineralized Makeup Water
- 12.
OTA - Data Logger ad0782-019Sg-93-154
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EQUIP ID: P-55A SYS: eve EQUIP ABBR~ p SEl~:V DESC:
- IAF:GING PUMP E!~UIP TYPE: PUMP Q-LIST==> Q: Q A: 2 E: -
N: D P: Q 0: Q C: -
S: Q X: Q
==========--
---==================== DATA=====================================
RESPON DEPT: M DATE LAST CHANGE: 04 21 87 DATE IN SERVICE: 12 31 7i UFI SYSTEM: 02360 UFI EQUIPMENT: 11340 NERC:
HIST FDr-(MAT: D HIST RETENT PER: 60 HIST RETENT INT.: MO BUS: B12 LOAD GROUP:
METERED:
SCHEME: Bi205 DATA SOURCE: CPCO SECONDARY SYSTEM: eve ASSOCIATION KEY: PALi0002000 PRIMARY CLEAN CLASS:
OPER LDC EQl IP ID: QLOG T86-91 SECONDARY CLEAN CLASS:
CATALOG RE:. NO: P
-0055A P.O.NUMBER: 1703692 P.O.YEAR:
MAJOR EQU *p ID:*
LIKE EQUIP ID:
PREV EQLIP ID: P-55 PREV EQ ID DATE: 11. 28 83 BLDG: AB r* Loor.;:: F2 JWOM: 104 ELEV:
590 LOC:
CHM~GING PUMP l\\OOM PORTABLE LCC:
TECH SPEC: SECT 3.2 <FSAR 5.7;* 9.10)
~===============================================~==============================
PF1=HELP PF2=NEXTLIST PF3=EQFLJNCT PF4=EQDATA1 PF5=EQDATA2 PF6=DRAWING PF7=ENGDAT 1 PF8=ENGDATA2 PF9=REPDATA PF10=INSTRUM PF1~=PRINT PF12=RETURN NEXTLIST:
PLANT: PAL UNIT:*
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\\\\-~\\t\\w\\~~t P~J.. D-t° Q-LIST CONSUMABLES TYPES AND INFORMATION THREAD SEALANT MATERIALS lhis section describes thread sealant TYPES Fluorocarbon base tapes (TFE type)
Graphite tapes Fluorocarbon-f il led polyester Polyester 1
POSITION ON USE Acceptable on joints only below 302°F and below 10 rads Acceptable Acceptable to 30f F and be low 10 rads Acceptable for specific a~plica tion only.
MANDATORY PRECAUTIONS Do not use on lines that will reenter the reac-tor system.
Start tapes between 2nd and 3rd thread or more.
CONSIDERATIONS Materials proper-ties deterioration with temperature and radiation ex-posure.
Materials contaminant levels and resulting cross-contamination of structural metallic materials.
Use only products See above listed. Start considerations.
tape between 2nd and 3rd thread or more to reduce particle drop-off.
"NF Primer" to See above speed cure is not considerations.
allowed on stain-less steels or nickel alloys.
See above considerations.
Used on small CRD valves where seats are screwed into valve body.
CCPM AITACHMENT 4-0P02 Revision 1 Page 42 of 53 BASIS FOR USE OR PROHIBITIONS Radiation resis-tance low.
Solu-ble halogen factor unknown.
Satisfactory use of graphite prod-ucts such as packings and lubricants over long periods in BWR systems.
Radiation resis-tance good.
- Primer is tri-clorethylene base Polyester is free of contaminants.
This application is in ambient temperature
- y
CO~SUMABLE Dow Corning DC-4 Dow Corning DC-41 Dow Corning DC-55M Dow Corning Molykote 44 Nedium Ezy Tap Fel Pro N-5000 Malinkrodt AR Type Fluid 5001 Ethylene Glycol Neolubt!.No 1 Never seez Pure Nickel Special Nuclear Teliaco 1999 WD-40 Acrylic Labels Carters Marks A Lot Black Crayons lfa:x Base Film Tape Ink Tipped Markers 'or Ball Point Pens Lay Out Flufd DX-100 Lay Out Fluid Dykem Steel Blue Lay Out Fluid SP.- llliO Metal Tags and Wires Nissen No Chloride White Metal Marker Paint Pencils Black Lead Pressure Se11sitive Labels Brady SB-3bl Soapstone (Talc Crayons)
Spray On 603 Magaflu:x Spot Check Penetrant Cleaner R1::mover Spot Check Penetrant Cleaner Developer Copalitite Fluorocarbon Base Grafoil Tape chesterton Grafoil Tcipe Crane Packing Grafoil Tape Durcimetaltc Graphite T<:p.: (Sepco Grafoil Nu.clear Grade)
Loctite \\i:.i.. F'luorcarbon Filled Polyester MFT.OP02
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PALISADES EVALUATED CONSUMABLES LlST TYPE Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Lube Speciality Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking.Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Marking Mtrl Mat;king Mtrl Marking Mtrl NDT 1-ltrl SS NDl Mtrl SS
'Sealant Thread Sealant Thread Sealant Thread Sealant Thread Sealant Thread Sealant TI1rt::ad Sealant Threi.d Dated:. 3/6/87 0 -r l ~..(:"<.Jy\\- tY\\ A.--1..l ci v CATEGORY A
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PALISADES NUCLEAR PLANT TECHNICAL SPECIFICATIONS SURVEILLANCE Revision and Approval Summary PROCEDURE TITLE:
CONTAINMENT SPRAY AND LPSI CHECK VALVE TEST
- 1.
- 2.
QA Concurrence 5/21fe1 Responsible Individual Date
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- 4.
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- 6.
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Periodic Review S/21/fz Date Date Date Date Date ts0381-0717g-89 Proc No Q0-10 Revision 11 Date 4/ 1/87
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- 1.
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- 3.
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Date Date Date Date hpl284-0006e-91-154
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Title:
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NUCLEAR OPERATIONS DEPARTMENT W
FAOUTY CHANGE MAJOR Plant
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- Equipment Pl1nt System Code!,__..____. _ _.
Processing Sequence Sign1ture D1te I Pl1nt Project No.
Conceptu1l Design Comolete Function1l
Description:
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0-List Affected?
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0 Yes 0 No*
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Detailed Design Inputs v I
Complete:
0 sign Plan sign Document
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list Functiona1 ""'""on Project Q*List Safety Evalu1tion Proj Eng PRC Action Mtg No./Oate Detailed Design Outpuu Complete.
Proj Eng Design Verification Complete Proj Eng Admin Project Review Complete Proj Eng ALARA Review Complete ALARACoord QA Review Complete QA Reviewer Notification of Modification Plant Operations*
Construction Work Packages Complete Proj Const Supt Spare Parts Ordered Plant Eng Installation, Inspection, Testing Complete Proj Mgr Operability Authorization Ops Supt Interim Turnover Review QA Dir/Supt Interim Turnover Accepted Plant Gen Mgr/Supt Final Turnover Review QA Dir/Supt Final Turnover Accepted Plant Gen Mgr/Supt Record Turnover Complete Proj Eng Closeout E&M Mgr/Supt Proi Mar Form 3170 3-7 8
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Power flflWUlllllli MIClll&All'S Amli<<£U Project No.
P.ADES NUCLEAR PLANT Facility Change - Minor Rt-\\--\\-~<:-\\A \\M.e.~ B f'~ e o rr !?.. F C-~I
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UFI No.~' --'---'-'-L'--'----'
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Plant System Code._I _.....___._...J System Equipment
Title:
Processing Sequence Date Prelim Engg Comp Functional
Description:
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Plant Projects Supt c Act in.a Mtg No./Date Detailed Engr Comp
_Proj Engr Proj Review Comp Plant Projects Supt ALARA.Review ClA Review ClA Authorization To *Implement Plant Mgr/Supt Operations Notified Proj Engr Completed, Inspected, Tested I
Proj Engr ClA Review ClA Supvr Operability Authorization Ops Supt Document Update Pi"oj Engr Closeout -
Plant Projects Supt Memo Form 3603 1-87
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tansumers Power
- POWERING MICHlliAN'S PROGRESS PALISADES NUCLEAR PLANT
~neering Design Change
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I 0-Listed Jl Yes fl No J 1\\1 Yes IJNo No. EDC-FC i
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n Design Change Design Error l
Drawing Error Additional Design Information Remarks
- .. n lacilitate Fabricat'ion
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LJFa1 ci.litate Construction/Installation LJ Construction Error II Other De5cription of Proposed Change (Attach Appropriate Analyses, Sketches, Drawings, as Required)
Effect on Hardware n None n Rework Design Documents Affected 0 Drawin.gs D Specifications D Procedures n Instructions n New I Effect on Schedule.
Design Change Effect on Original Safety Evaluation n None n New Safety Evaluation Required*
Prepared by Technical Review Attachments n Yes n No
- New Safety Evaluation requires review equivalent to the original evaluatiO!:J Date Date I
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,__ ______________________ **- ----------~-----------------------l-----------------1 EEO Review (if EEO-Listed I Date EEO Engineer Quality Assurance Review (if 0-Listed)
Date 1-------------------------------------------------+---------------'-I Administrative Review and Approval Date Plant Projects Superin_te.ndent Memo Form 3685 1-87.
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DESCRIPTION System UFI Equipment PAJ.JSADES PLANT Jumper, Link and Bypass UFI Jumper, Link and Bypass Description -
Fill in First Three Columns of Installation Removal Section (*)
Reason tor Jumper, Link and Bypass Applicable Drawings equester Date REVIEW Technical Review Note:
Technical reviewer to document his review method on the back of form.
PRC Member Review (If Immediate and 0-Listed)
SRO Review (If.Immediate and 0-Listed)
PRC Review (If 0-Listed)
INSTALLATION/REMOVAL Work Order Numbedor lnstanatlon Shift Supervisor Authorization for Installation Work Ordef" Number for.Removal Shift Supervisor Authorization for Removal
- Item -
eg, Jumper, Link
- Location - eg, Panel, Terminal Strip No., Link No.,
~Operation - eg, Open, Installation Wire Blank Flange Room No. J Box No.
Removed Placed Performed bv/Date
~aution Tags Placed by Caution Tags Removed by Memo Form 3621 3'.a7 I nstal lat ion Verified by/Date Date Date Date Date Date Date der Number allation/Removal Section Removal Removal Performed bv/Date Veri tied bv /Date Date Date
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TECHNICAL REVIEW PROCESS Is jumper, link and bypass located on the correct terminals, links, connectors, etc?
Will the jumper, link and bypass achieve the desired result?
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Will the jumper, link and bypass render equipment required by technical specifications inoperable? If so, justify.
Is the jumper, link and bypass consistent with applicable codes or standards (ASME, i EEE, EEO, etc)?
QUARTERLY REVIEW Name Date Remarks Prints and Procedures Updated
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Operations Superintendent Review - Name and Date Remarks I
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/lllCHlliAll"S PRDliRllS WO/PO Original Spec Number/Date/Revision Uniform File System Index I
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I PALISADES PLANT Specification Change Equipment I
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System Equip.ment Code I
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Equipment Number Serial Number Part Number Stock Number 1
2 3
4 Item Original Requirements Changed to References Reason for Change v~~ =- s*~ ~Q\\~~
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'Date Q-Listed I
Date a; PRC Review (If 0-Listed)
Yes No Action Complete*
Date I
NPR OS Update 1'...
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- These act1v1t1es not required for Procurement Documents.
- see Specification Change Checklist.
Memo Form 3607 8-86
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Tech Review - Fune Supt I
Date QA Review (If 0-Listed)
Date Closeout Plant Proj Supt*
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