ML19350D537

Forwards Request for Addl Info Re FSAR QA Program.Items to Be Added to QA List:Quencher & Quencher Support,Downcomers & Braces Containment Spray Sys,Hydrogen Recombiners & Instrument Storage,Calibr & Maint

ML19350D537
Person / Time
Site:	Zimmer
Issue date:	03/25/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Borgmann E CINCINNATI GAS & ELECTRIC CO.
References
NUDOCS 8104160480
Download: ML19350D537 (8)

Text

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h MAR 2 5 193)

Distribution Docket File NRR Reading NRC POR Local PDR '- ' :

L3 2 File Cocket No. 50-358 D. Eisenhut R. Purple R. Tedesco Mr. Earl A. Borgmann A. Schwencer Vice President - Engineering I. Peltier Cincinnati Gas & Electric Company M. Service P. O. Box 960 IE (3)

Cincinnati, Ohio 45201 bec: ACRS (16)

Dear Mr. Borgmann:

NSIC

SUBJECT:

'4m. H. Zimer Q-List Review The NRC staff has completed its review of the Qtmmer FSAR Quality Assurance Program, specifically Table 3.2.1, " Structures, Equipment, and Component Classi fications." Certain deficiencies are suspected and these are listed in the enclosure to this letter. Enclosure 250 lc reflects the requirements of MUREG-0737, " Classification of TMI Action Plan Requirements " (November 1980).

Please advise when you plan to respond to the enclosure. 'de will be happy to discuss this matts. with you to expedite resolution.

Sincerely.

Original signed by Robert L. Tedesco Robert L. Tedesco Assistant Ofrector for Licensing Division of Licensing

Enclosure:

l Request for Additional 4,5 t #

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W 2 5 193' Mr. Earl A. Borgmann Vice Presicen: - Engineering Cincinnati Gas 1 Electric Company P. O. Box 960 Cincinnati, Ohio 45201 Troy 3. Conner, Jr., Esq.

Lean S. Kosik Esq.

cc:

Conner, Mcore L Corcer 3:54 Cornell Place 1747 Pennsylvania Avenue, N.W.

Cincinnati, Onio 45220 Washington, 0.C.

20006 Mr. William J. Mcran W. Peter Heile, Esq.

General Counsel Assistant City Solicitor Recm 214, City Hall Cincinnati Gas & Electric Ccepany Cincinnati, Ohio 45220 P. O. Box 960 Cincinnati, Ohio 45201 Jenn D. Woliver, Esc.

Mr. William G. Pcrter, Jr.

Clermont Ccunty Cc= unity Council Box 181 Porter, Stanley, Artnur 5atavia, Chio

~5103 and Plat:

37 West 3rcad Street Mrs. Mary Recer Columbus, Ohio 43215 304 270, Rt. 2 Mr. James D. Flynn, Manager California, Kentucky 41007 Licensing Environmental Affairs Cincinnati Gas & Electric Ccmcany Ancrew 3. Dennison, Esq.

200 Main 5:ree:

?. O. Box 950 3atavia, Cnio 45103 Cincinnati, Ohio 45201 Cavid Martin, Esq.

Rober: A. Jones, Esq.

Office of the A::orney General Prosecuting A :ceney of Clerment 2G9 St. Clair Street County, Ohio 154 Main Street First Floor Batavia, Ohio 45103 Frankfort, Xentucky 4C601 Residen Inspector /Zi=er Dr. Frank F. Hooper RF0 1, P. O. Box 2021 School of Natural Resources U. S. Route 52 University of Michigan Mosccw, Ohio 45153 Ann Arcor, Michigan 48109 Mr. Jonn Youkilis Charles Bechheefer, Esq., Chairman Atcmic Safety & Licensing Board Panel Office of The Honorable William Gradison United States House of Representatives U.S. Nuclear Regulatory Co. mission Washington, D. C.

20515 Washing:cn, D.C.

20555 Mr. Glenn O. Bright Atomic Safety & Licensing Board Panel

' U.S. Nuclear Regulatory Comission Wasnington, D.C.

20555 P00R ORIGINAL.

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REQUEST FOR ADDITIONAL INFORM TION Zinner Nuclear Pcwer Station 260.0 Quality 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-Tist) controlled by the QA program. You are requested to supplement and clarify the Q-list in Table 3.2.1 of the FSAR in accordance with the following:

The following items do not appear on the Q-list (FSAR Table 3.2.1).

a.

Add the appropriate items to the Q-list and provide a ccmmitment tha; the remaining items are subject to the pertinent requirements of the FSAR cperational QA program or justify not doing so.

1) Quencher and quencher support.

2) Cowncomers and braces.

3) Containment spray system.

4) Pri:rary containment access hatches / locks / doors, ::enetration assemolies, and vacuum relief valves.

5) Piping of condensate and feedwater systems frcm reactor pressure vessel to outermost centainment isolation valves.

6) Hydrogen reccmbiners.

7) Radiation monitoring (fixed and portable).

8) Radioactivity monitoring (fixedgnd portable).

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

10) Radioactive contaminaticn measuremnt and analysis.

li) Personnel moni oring internal (e.g., whole body counter) and external (e.g., TLD system).

12) Instrument storage, calibration, and maintenance.

13) Cecontamination (facilities, personnel, and equipment).

14) Respiratory protection, including testing.

15) Contamination control.

16) Radiation shielding.

17) Feedwater spargers.

18) Expendable and consumable items necessary for the functional performance of safety-related structures, systems, and compo-nents (i.e., weld rod, fuel.ofl, boric acid, snubber oil, etc.).

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19) Measuring and test equipment used for safety-related struc-tures, syste.as, and components.

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

21) Meteorological data collection prograes.

22) Relief valve discharge piping.

23) Spent fuel poci liner.

' 24) Main steam piping frem cutermost isolation valves to turbine stoo valves.

25) Main steam branch oiping to first valve closed or capable of auto-matic actuation.

25) Main turbine bypass piping to by? ass valve.

27) First valve that is either nortally closed or capable of auto-atic closure in branch piping connected to main steam and turbine bycass piping.

20) MS!V leakage centrol system downstream piping frca steamline con-necticn to first valve.

29) RCIC turbine.

30) Auxiliary building.

31) Service water pump structure.

32) Service water pipe supports and encasements.

33) MSIY Leakage Centrol System a) Piping, within RCPB isolation valve.

b) Piping, other upstream system lines.

c) Piping, dcwnstream system from steamline d) Piping, other dcwnstream system lines, e) Valves, within RCPB.

f) Valves, other.

g) Heater.

h) 31cwers.

34) Refueling bellows, reactor cavity.

35) Biological shieldine within reactor building, auxiliary building,

- radwaste building, turbine building, and off-gas filter building.

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36) Missile barriers within reactor building, auxiliary building, and steam tunnel.

37) OnsitePcwerSystem(ClasslE) a) Diesel. generater packages including auxiliaries (e.g. lube system, jacket cooling, air start system, governor, voltage regulator, excitation system).

b) 4160V switc5 gear.

c) 180V load : enters.

d) 480V mater control centers.

t e) Cenduit and cable trays and their su;;crts.

[RacewayinstallattenscentainingClasslEcablesand other raceway installations required to meet seismic Category I requirements (those wnese failure may result in damage to a safety-related item).]

f.

Tran sfo rmers, g) Valve operators.

h) AC vital bus distributien ecui; ment.

1) Cable penetraticns (fire stops).

38) DC Power Systems (Class lE) a) Station batteries.

,s b) Battery chargers.

c) Battery racks.

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Inverters.

e) DC switchgear and distribution panels.

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The following items from the Q-list (FSAR Table 3.2.1) need expansicn and/or clarification as noted. Revise the list as indicated or jus-tify not doing so.

1.

Identify the safety-related instrumentation and control' systems and components to the same scope and level of detail provided in Chapter 7 of the FSAR.

2.

The structural aspects of "Other internal structures" (Iten I.7) should be under the pertinent requirements of the FSAR operational 4

QA program.

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. Enc!asure 2 of NUREG-0737, " Clarification of TMI Acticn Plan Require-c.

rents * ('iovember 1980) identified numerous items that are safety-related and appropriate for OL application and therefore should be on the 0-1ist. These items are listed below. Add the appenpriate items to the Q-list and provide a cemitment that the remaining items 3re subject to the pertinent requirements of the FSAR opera-ticnal CA program or justify not doing so.

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NUREG-0737 (Enclosure 2)

Clarificatien Item

1) Plant-safety-parameter display censole.

I.D.2

2) Raset:r c:clant system vents.

II.B.1

3) Plant shielding.

II.3.2 a) Post ac:ident sampling ca: ability.

II.3.3 5; 'laiva positien indicatien.

II.O.3

5) Cedicated hydrcgen penetrations.

II.E.4.1

7) C:ntainrent isolatten dependability.

II.E.a.2

8) Ac:ident rmnitoring instrumentatten.

II.F.1

9) Instrunentation for detection of inade-II.F.2 quate core-cooling.

10) HPCI & RCIC initiation levels.t II.K.3(13)

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Isolation of HPCI & RCIC.

II.K.3(15)

12) Challenges to and failure of relief II.K.3(16) valves.

13) ACS actuation.

II.K.3(18) la) Restart of core spray and LPCI II.K.3(21 )

15) RCIC suction.

II.K.3(22)

16) Space ecoling for HPCI & RCIC.

II.K.3(24)

17) Power on pumo seals.

II.X.3(25)

18) C m:~:n reference level.

II.X.3(27)

19) ACS valve, accumulators, and asscciated II.X.3(23) equi: ment and instrumentation.

, 20) Emercency plans.

III.A.l.1/III.A.2 21 ) Errergency sucpert facilities.

III.A.1.2

22) Inplant I2 radiation monitoring. -

III.D.3.3

23) Control-rcem habitability.

III.D.3.4

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