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DISTRIBUTION:
5 E g(P G III udocket File 8[(,f,.,V,U QA8 Projects o
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Itsbert L. Tedeses. Assistant Director for Licensing, 4
Mvisten of Licensing FMMt Walter P. Maass. Olief. Quality Assurance Branch.
Mvisten of Engineering SWJECT:
WAftlWORD Q-LIST IEVIEW am has asupleted its revleu of Table 3.2-1. " Classification of Structums, Sys-y sens. and Coupements.' which identifies items seject to Louisiana Power and Light Company's aparettenal QA program of the FSAR for Waterford.
Under the procedum that tavolves retten of tis Ifst by other NRR technical branches, we have iden-tifled eartete deffetencies uhtch are noted in the enclosure. Enclosum item 260.14 reflects te requirements of NUIEH737. "Clartfication of TMI Action Plan
'equimasets." (Itsuuter 195). Please transmit the request for additional infor-nation to me Laufsfone Power and L1 Wit Campany.
are available to discuss this matter eith you, your staff, and the Louisiana mer and L19tt Coupesy as may be required to expedite resolution.
Odeines sipod by
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Walter P. Naass. Difef Quality Assurance Branch Ofvisten of Engineering f.,
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FICIAL RECORD COF'Y P" !*
QT WATERFORD Request for Additional Information 260.1 Section 17.1.2.2 of the standard format (Regulatory Guide'1.70) requires i
the identification of safety-related structures, systems, and components r
controlled by the QA program.
You are requested to supplement and clarify Table 3.2-1 of the Waterford FSAR in accordance with the following:
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Note 13 to FSAR Table 3.2-1 apparently addresses quality assurance E:@, '
thering the design and construction phase (past tense). Clarify I
Note 13 or add a new note to show which structures, sys tems, and P
components of Table 3.2-1 will be subject to the pertinent require-p r.,
monts of the 10 CFR 50 Appendix 8 Quality Assurance Program during b
the operation phase of Waterford-3.
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The following items do not appear on FSAR Table 3.2-1.
Add the appropriate items to the table and provide a comitment that the
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remaining items are sdject to the pertinent requirements of the
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FSAR operational quality assurance program or justify not doing so.
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1.
Safety-related masonry walls (see IE Bulletin No. 80-11).
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[f 81ological shielding within containment, reactor building, 2.
reactor auxiliary building, and fuel handling building, b.
3.
Missile barriers within containment, reactor butiding, reactor aus111ary building, fuel handling building, and around air in-
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takes vent stacks, and other outside structures, as applicable.
4.
Refueling water storage pool (integral part of reactor auxiliary building structure).
5.
Condensate storage building structure) pool (integral part of reactor auxiliary 6.
Radiation monitoring (fixed and portable).
7.
Radioactivity monitoring (fixed and portable).
8.
Radioactivity sampling (air, surfaces, liquids).
9.
Radioactive contamination measurement and analysis.
- 10. Personnel monitoring internal (e.g., whole body counter) and external (e.g., TLD system).
11.
Instrument storage, calibration, and maintenance.
12.
Decontamination (facilities, personnel, and equipment).
13.
Asspiratory protection, including testing.
'14.
Contamination control.
15.
Radiation shielding (pemanently. ins talled).
- 16. Accident-related meteorological data collection equipment.
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..;. Expendable and consumable items necessary for the functional 17.
perforinence of safety-related structures, systems, and compo-nonts (i.e., weld rod, fuel oil, boric acid, snubber of1, etc.).
- 18. Measuring and test equipment used for safety-related struc-tures, sptoms, and components.
- 19. Trisodius phosphate baskets.
- 20. Instruentation related to the controlled ventilation area system (p. 3.2-12).
- 21. Effluent radiation monitoring (p. 3.2-14).
- 22. Transfomers (2) and motor control centers (2) in the cooling teser areas.
- 23. Onsite Power Systans (Class 1E) a) Instrumentation, control, and power cables including underground cable system, cable splices, connectors, and terminal blocks, Conduit, cable trays, and their supports.
(Installa-b) tions containing class IE cables and those whose fail-ure during a seismic event may damage other safety-related items.)
c) Valve operators.
d) Containment electrical penetration assemblies.
e) ' Other cable penetrations (fire stops).
- 24. DC Power Systems (Class 1E) a) Cables.
Conduit, cable trays, and their supports.
(Installa-b) tions containing class 1E cables and those whose fail-are during a seismic event may damage other safety-reisteditems.)
c) Protective relays and control panels.
- 25. Spent fuel cask.
- 26. Spent fuel handling machine.
- 27. Nfuelingmachine.
- 28. CEA change mechanism.
- 29. Fuel transfer system.
- 30. Spent fuel handling tool.
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- 31. Steam generator piping located inside containment.
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- 32. Containment spray system sump and sump screen.
- 33. Com6ustible gas control piping and valves.
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- 34. Containment vacuum relief actuation system.
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Containment pressure indication system.
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- 35. Containment water level indication system.
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- 37. Containment hydrogen indication systan.
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- 38. Valve operators for safety-related valves.
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3D. Motors for safety-related pumps.
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The following items from the FSAR Table 3.2-1 need expansion and/or i
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clarification as noted.
Revise the list as indicated or justify not M
doing so.
g 1.
Identify the safety-related instrumentation and control sys tems
[d to the same scope and level of detail as provided in Chapter 7
[g-c of the FSAR.
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2.
Clarify that the particulate filters, charcoal absorbers, and radiation monitors for the following systems will be subject to the pertinent provisions of the FSAR Section 17.2 quality i
assurance program during the operational phase:
M a) Fuel handling building ventilation system (p. 3.2-11).
p b) Shield building ventilation system (p. 3.2-12).
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c) Controlled ventilation area system (p. 3.2-12).
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d) Control room habitability (p. 3.2-10).
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3.
Clarify that the UHS sep pumps (p. 3.2-14) will be subject to the pertinent provisions of the FSAR Section 17.2 quality assur-ance program during the operational phase.
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- d. of NUREG-0737. " Clarification of TMI Action Plan Require-monts" (November 1980) identified numerous items that are safety-m1ated and appropriate for OL application and therefore should be on Table 3.2-1.
These itens are listed below.
Add the appropriate items to Table 3.2-1 and provide a comitment that the remaining items are subject to the pertinent requirements of the FSAR operational quality assurance program or justify not doing so.
NUREG-0737 (Enclosure 2)
Clarification Item
- 1) Plant-safety-parameter display console.
I.D.2
- 2) Reactor coolant systen vents.
II.B.1
- 3) Plant shielding.
II.B.2
- 4) Post accident sampling capabillties.
II.B.3
- 5) Valve position indication.
II.O.3
- 6) Auxiliary feedsater systam.
II.E.1.1
- 7) Auxiliary feessater systee initiation and II.E.1.2 flow.
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- 8) Emergency power for pressurizer heaters.
II.E.3.1
- 9) Dedicated hydrogen penetrations.
II.E.4.1
- 10) Cantainment isolation dependability.
II.E.4.2
- 11) Accident monitoring instrumentation.
II.F.1 fi W) lastmeentation for detection of inadequate II.F.2 core-cooling.
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- 13) Power supplies for pmssurizer level indica-II.G.1 tors.
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14)
Automatic trip of reactor coolant pumps.
II.K.3(5)
- 15) Paper en pump seals.
II.K.3(25)
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- 16) Emergency plans (and related equipment).
III.A.1.1/III.A.2 5
- 17) Equipment and other items associated with the III.A.1.2 l
emergency support facilities, i
- 18) Inplant 12 radiation monitoring.
' III.D.3.3 i
- 19) Control-room habitability.
III.D.3.4 l
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