ML19341D139

Forwards Request for Addl Info Re Q-list Review for Facility.Util Must Provide Justification for Omitting Following Items:Radiation Monitoring,Instrument Storage Calibr & Maint,Fuel Assemblies & Containment Control

ML19341D139
Person / Time
Site:	McGuire, Mcguire
Issue date:	02/20/1981
From:	Noonan V Office of Nuclear Reactor Regulation
To:	Tedesco R Office of Nuclear Reactor Regulation
References
NUDOCS 8103041030
Download: ML19341D139 (7)

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50-370 MEMORANDUM FOR:

Robert L. Tedesco, Assistant Director for Licensing, Division of Licensing FROM:

Vincent S. Noonan, Assistant Director for Materials &

Qualifications Engineering, Division of Engineering

SUBJECT:

Q-LIST REVIEW, f1CGUIRE NUCLEAR STATION UNIT NOS.1 & 2 QAB has completed its review of Section 3.2 of the FSAR for the McGuire Nuclear Station, Unit Nos.1 & 2 which identifies the structures, systems, and compo-nents subject to the Duke Power Company Operational QA Program. Under a revised procedure that involves other NRR technical review branches in the review of this list, we have identified certain deficiencies which are noted in the enclo-sure.

Item c of the enclosure reflects the requirements of NUREG-0737, "Clari-fication of Tit! Action Plan Requirements " (November 1980).

Please transmit the enclosed request for information to the Duke Power Company.

We are available to discuss this matter with you, your staff. and Duke Power Company personnel as may be required to expedite resolution.

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i Vincent S. Noonan, Assistant Director for Materials &. Qualifications Engineering Division of Engineering

Enclosure:

Request for Additional Infomation cc w/ enclosure:

B. J. Youngblood R. Birkel H. Levin 8103 04p 1030 L

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REQUEST FOR ADDIT 0NAL INFORMATION McGuire Nuclear Station Unit Nos.1 & 2 260.0 puality Assurance Branch 260.1 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 suppleaent and clarify the Q-list (Table 3.2) in the FSAR in accordance with the following:

1 a.

The following items do not appear on the Q-list. Add these items or justify not doing so.

1) Measuring and test equipment used for safety-related struc-tures, systems, and components.

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2) Masonry walls per IE Bulletin No. 80-11.

3) Radiation monitoring (fixed and portable).

4) Radioactivity monitoring (fixed and portable).

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

6) Radioactive contamination measurement and analysis.

7)

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

8)

Instrument storage, calibration, and maintenance.

9)

Decontamination (facilities, personnel, and equipment).

10)

Respiratory protection, including testing.

11 ) Contamination control.

12)

Fuel assemblies.

13) Control rod assemblies.

14)

Core support structure.

15) Reactor vessel internals other than items 12,13, and 14 above.

16)

Control rod drive mechanisms.

r 17)

Pressurizer spray nozzles.

18) Steam generator steam flow restrictors.

19) Sampling system delay coils up to and including the containment isolation valve.

.. 20) Sampling system lines connected to safety system components up to and including the isolation valve or block valve.

21) Spent fuel storage racks.

22) On-site Power Systems (Class lE) a.

Diesel generator package including auxiliaries (e.g., gover-nors, voltage regulator, excitation system).

b.

Protective relays and control panels.

c.

Containment electrical penetration assemblies, d.

Other cable penetrations (fire stops).

23) DC Power Systems (Class 1E) a.

Battery racks.

b.

Protective relays and control panels.

24)

Expendable and consumable items necessary for the functional per-formance of critical structures, systems, and components (i.e.,

weld rod, fuel oil, boric acid, snubber oil, etc.).

25) Tornado missile protection for the refueling water storage tank.

26) Meteorological data collection programs.

27) Post accident monitoring instrumentation.

28) Essential heating and ventilation.

29) Missile barriers protecting safety-related equipment, including missile barriers around air intakes, vent stacks, and other out-side structures as applicable.

30) The Leak Detection System discussed in FSAR Section 5.2.7 should be explicitly identified, or all of its constituent parts should be included as sub systems or components of other entries on the Q-list.

31 )

Pressurizer relief piping from pressurizer to the pressurizer drain tank.

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32) Biological shielding within containment and auxiliary buildings and other radiation shielding.

33) Non-safety systems that penetrate containment and are an exten-sion of the containment boundary up to and including the contain-ment isolation valves.

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34) Residual heat removal system piping, spray headers, spray noz-zies, and related supports.

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35) Containment spray system piping, spray headers, and related supports.

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36) Annulus ventilation system ducting and supports.

37)

Ice basket supports.

38) Supports for cor tainment isolation system valves.

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39) Ducting and. supports for the containment air return and hydro-j gen skimmer system.

40) Ducting, supports, dampers, and operators for the ES air hand-ling units of the auxiliary building ventilation system.

41) Hydrogen analyzer system.

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42) Containment pressure indication systems.

43) Containment sump level indication systems.

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The following items from the Q-list need expansion and/or clarification.

Revise the list as indicated or justify not doing so.

1) Clarify that the Q-list includes the pressurizer PORVs and 4

associated block valves (including their actuators).

2) Clarify that main steam isolation valves are included on the Q-list.

It is not clear from the designation "D" in Table 3.2.2-2 whether main steam isolation valves are "Q required."

3) Clarify that main steam piping (S.G. to MSIV) is included on the Q-list.

4) Clarify that the containment sump, sump screen, and vortex sup-pression devices are included on the Q-list.

5) Clarify what is meant by " selected" in Table 3.2.3-1.

When applied to valve motors or solenoids, exempted valves should be justified specifically by their function (s) or lack thereof.

l 6)

Identify the safety-related instrumentation and control systems l

to the same scope and level of detail as provided in Chapter 7 l

of the FSAR.

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7) Clarify that " Containment" (Table 3.2.1-1) includes (a)

Personnel access hatches and associated seals, valves, piping, and tanks.

(b) Equipment access hatch and seals.

(c) Divider barrier seal.

8) Clarify'that operators of valves which require safety related quality assurance also require safety related quality assurance, i

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c. of NUREG-0737, " Clarification of 1MI Action Plan Require-ments," (November 1980) identifies numerous items that are safety-related and appropriate for OL application and therefore should be on the Q-list. These items are listed below. Add these items to the Q-list and/or indicate where on the Q-list they can be found. Other-wise justify not doing so. '

NUREG-0737 (Enclosure 2)

Clarification Item

1) Plant-safety-parameter display console.

I.D.2 2

2) Reactor coolant system vents.

I I. B.1

3) Plant shielding.

II.B.2

4) Post accident sampling.

II.B.3 4

5) Valve position indication.

II.D.3

6) Auxiliary feedwater system.

I I. E.1.1 i

7) Auxiliary feedwater system initiation II.E.1.2 and flow.

8)

Emergency power for pressurizer heaters.

II.E.3.1

9) Dedicated hydrogen penetrations.

II.E.4.1

10) Containment isolation dependability.

II.E.4.2

11) Accident monitoring instrumentation.

I I. F.1 12)

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

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

14) Automatic PORY isolation.

II.K.3(1)

15) Automatic trip of reactor coolant pumps.

II.K.3(5)

16) PID controller.

II.K.3(9)

17) Anticipatory reactor trip, on turbine trip.

II. K. 3(12 )

18)

Power on pump seals.

II.K.3(25)

19) Emergency plans.

III. A.l.1/III. A.2

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Emergency support facilities.

III.A.1.2 21)

Inplant Ip radiation monitoring.

III.D.3.3

22) Control-room habitability.

III.D.3.4

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