ML20003C306

Forwards Request for Addl Info Re NRC Review of FSAR Chapter 3,including Sys,Structures & Components Subj to Operational QA Program.Response Should Be Provided by 810213

ML20003C306
Person / Time
Site:	Summer
Issue date:	01/28/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Nichols T SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 8102270669
Download: ML20003C306 (6)

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Docket No. 50-395 DN281981

/d M db4 O8 h G3F Mr. T. C. Nichols, Jr.

P Vice President & Group Executive f4 i f0g3 Nuclear Operations p.Movo" f7 South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281

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SUBJECT:

Q-LIST REVIEW FOR VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 The Quality Assurance Branch has completed its review of Chapter 3 of the FSAR for the Virgil C. Summer Nuclear Station, Unit No.1, which identifies the structures, systems, and components subject to your Operational Quality Assurance Program.

Under a revised procedure that involves other NRR technical review branches in this review, we have identified certain deficiencies and have generated the enclosed request far additional information.

Your response to the enclosed request should be provided not later than February 13, 1981.

Please contact the staff's assigned project manager if you require any clarification of these matters.

Sincerely.

kLe-s <J Robert L. Tedesco Assistant Director for Licensing '

Division of Licensing

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Enclosure:

Request for Additional Information cc w/ enclosure:

See next page l

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02 27n Q

Mr. T. C. Nichols, Jr.

Vice President & Group Executive d4#28 Jog; Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281 cc: Mr. William A. Williams, Jr.

Vice President South Carolina Public Service Authority 223 Nort.. Live Oak' Drive Moncks Corner, South Carolina 29461 J. B. Knotts, Jr., Esq.

Debevoise & Liberman 1200 17th Street, N. W.

Washington, D. C.

20036 Mr. Mark B. Whitaker, Jr.

Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1, Box 93C Li'.tle Mountain, South Carolina : 29076 Resident Inspector / Summer NPS c/o U. S. NRC Route 1, Box 64 Jenkinsville, South Carolina 5

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REQUEST FOR ADDITIONAL IflFORMATION Virgil C. Summer Nuclear Station 420.0

' Quality Assurance Branch 420.83 Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures, systems, and components (Q-list) controlled by the QA program.

You are requested to supplement and clarify the Q-list in Tables 3.2-1, 3.2-2, 3.10-1, and 3.10-2 of' the FSAR in accordance with the following:

The following items do not appear on the Q-list. Add these items or a.

justify not doing so.

1) Biological shielding within reactor building, control building, auxiliary building, fuel handling building, and intermediate building.

2) Missile barriers protecting safety-related equipmant within the reactor building, control building, auxiliary building, fuel handling building, intermediate building, diesel generator baild- --

ing pump house, and around air-intakes, vent stacks, and other outside structures es applicable.

3) Pressurizer spray nozzles.,

4) Steam generator steam flow restrictors.

5) Fuel handling building crane.

6) Meteorological data collection programs.

7) Steel liner of the reactor building.

8) Supports for containment heat removal system.

9) Combustible gas control system a) H2 purge supply and exhaust system b) H2 monitoring system c) H2 analyzer d) Supports

10) Containment emergency cooling system a) Cooling coils b)

Ductwork dampers and supports

11) Onsite power systems (Class IE) a)

Diesel generator packages including auxiliaries (i.e., governor, voltage regulator, excitation system) b) 4160 volt switchgear c) 480V load centers d) 480V motor control centers e)

Instrumentation, control, and power cables (including underground and_ terminal blocks) torsm

. f)

Conduit and cable trays and their supports Note--Raceway installations containing Class 1E cables and other raceway installations required to meet seismic category 1 requirements (those whose failure during a seismic event may result in damage to any Class lE or other safety-related system or components) should be included.

g)

Transformers h)

Valve operators i)

Protective relays and control panels j) AC control power inverters k) 120 AC vital bus distribution equipment 1)

Containment electrical penetration assemblies m)

Other cable penetrations (fire stops) 12)

DC power systems (Class IE) a)

125V battery, battery chargers. and distribution equipment b)

Cables c)

Conduit and cable trays and their supports Note--Raceway installations containing Class lE cables and other raceway installations required to meet seismic --

category 1 requirements (those whose failure during a seismic event may result in damage to any Class IE or other safety-related system or components) should be included.

d)

Battery racks e)

Protective relays and control panels 13)

Reactor building charcoal cleanup plenums.

14)

Reactor building purge exhaust plenum.

15)

Controlled access area charcoal exhaust plenum.

16)

Process and effluent radiation monitoring systems.

17)

Auxiliary building charcoal filter system plenum.

18)

Buried service water piping systems.

19)

Safety-related masonry walls (see IE Bulletin No. 80-11).

Expendable and consumable items necessary for the functional perform-20) ance of CSSC (i.e., weld rod, fuel oil, boric acid, snubber oil, etc.).

21)

Measuring and test equipment..

22)

Leak detection system (per FSAR Section 5.2.7).

23)

Pressurizer safety and relief valves, block valves, and associated a c tua tors.

24)

Steamline safety valves and PORVs.

25)

Pressurizer discharge line to pressurizer drain tank.

26) Containment sump, sump screen, and sump vortex suppression devices.

27) Radiation monitoring (fixed and portable).

28) Radioactivity monitoring (fixed and portable).

29) Radioactivity sampling (air, surfaces, liquids).

30) Radioactive contamination measurement and analysis.

31)

Personnel monitoring internal (e.g., whole body counter) and external (e.g., TLD system).

32)

Instrument storage, calibration, and maintenance.

33) Decontamination (facilities, personnel, and equipment).

34) Respiratory protection, including testing.

35) Contamination control. of NUREG-0737, " Clarification of TNI Action Plan Requirements" b.

(November 1980) identified numerous items that are safety-related and appro-priate for OL application and therefore should be on the Q-list for the These items are listed below. Add these Virgil C. Summer Nuclear Station.

items to the Q-list and/or i:idicate where on the Q-list they can be found.

Otherwise justify not doing so.

NUREG-0737 (Enclosure 2)

Clarification Item

1) Plant-safety-parameter display console.

I.D.2 II.B.1 2)

Reactor coolant system vents.

II.B.2 3)

Plant shielding.

II.B.3

4) Post accident sampling.

II.D.3

5) Valve position indication.

6) Auxiliary feedwater system.

II.E.1.1 II.E.1.2

7) = Auxiliary feedwater system initiation and flow.

II.E.3.1 8)

Emergency power for pressurizer heaters.

II.E.4.1 9)

Dedicated hydrogen penetrations.

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o 4-10)

Containment solation dependability.

II.E.4.2

11) Accident monitoring instrumentation.

II.F.1 12)

Instrumentation for detection of inadequate II.F.2 core-cooling.

13) Power supplies for pressurizer relief II.G.1 valves, block valves, and level indicators.

14) Automatic PORV isolation.

II.K.3(1)

15) Autcmatic trip of reactor coolant pumps.

II.K.3(5)

II.K.3(9) i 16)

PID controller.

17) Anticipatory reator trip on turbine trip.

II.K.3(12) 18)

Power on pump seals.

II.K.3(25)

III.A.l.1/III.A.2 19)

Emergency plans.

20) Onergency support facilities.

III.A.l.2 radiation monitoring.

III.D.3.3 21)

Inplant 12 22)

Control-room habitability.

III.D.3.4 The instrumentation and control systems and components must be identified c.

on the Q-list to the same scope and level of detati provided in_ Chapter 7 of the FSAR.

(Tables 3.10-1 and 3.10-2.are too general.)

Include safety-related display instrumentation such as source range neutron flux monitors.

Also include applicable items listed in Section 3.11.

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