ML20042C676

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Forwards Addl Info Re SER Table 3.2-1, Design Criteria Summary
ML20042C676
Person / Time
Site: Midland
Issue date: 04/27/1982
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Jackie Cook
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8205070087
Download: ML20042C676 (5)
v • d • e


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NW 2 71982 Decket nee: m ats and 90,330

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Ier. J. W. Cask 4

Vtes President

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Canossers Peuer C ureny

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1945 W. Pernell Road

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Jackssa. 8tichigan 49201 a

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Rogeest for Additional Information on Midland Plant,

)l plu 1 W 2 The IRC Staff is fina11aing its review of the Midland Final Safety Analysis U

Soport DIAR) prior to issuance of en SER. In the cour.e of this review,

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to Quality Assurance trench identified additional information regar<11ng Table 3.2 1 (" Design Criteria Swanary"). The enclosure to this letter identffles De specific deficiencies noted during this review.

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The sectosure mes given to mem6ers of your staff and br'erly discussed with j

i them during te SER spee iten resolution meeting on April 6, 1982. At that time your staff indicated that they would initiate action to resolve the 7[

ttems.' Thfs voquest is foresi documentation of the verbal request made on Aprf) 6.

A telephone conference was held on April 20, 1982, to further discus le the tehneetten en the enclosure. Should you have any guestions on the i

ottacted, contact Mr. R. W. Wernen at (301) 492-8395.

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The reporting end/or recereceping requirements contained in this letter L,

effect fewer.than ten respondents; therefore, Of9t clearance is not recuired undar P.L.96-611.

L Sincerely, y

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Robert L. Todesoo 1

4 Robert L. Tedesco, Assistant Of rector for Licensing Division of Licensing L

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260.0 Quality Assura,nce Branc_h 260. I Section 17.1.E.? of the standard f ormat ( W,,1 2 tory to.

the iden ti f icat ion of s a fe ty-re l a te d ',' e ar f ures, <,;. s to--

m, controlled by the QA pmgrat':.

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rowe-ted ta s e., ' o r -

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fy Table 3.2-1 of the Midland F5AF ir..utordance wie t'.

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The following items do not appear en PiAR Table.!. 2.

A ti appropriate items to the table and provide a con. t try <. tr the remaining items are subject to the pertinent re 2J1' erro-of the FSAR operational quality assurance progreT e-

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e not doing so.

1.

Safety-related m6sonry walls (see IE Builetin '.-

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2.

Biological shielding within the aup t liary build;r.g ar.'

reactor building.

3.

Missile barriers within the reactor building, aJ3) ita*

building, diesel-generator building and service wato' pump structure as appropriate.

4 Spent fuel pool and liner.

5.

Pressurizer PORY block valve.

6.

Control rods.

7.

Control rod drives.

8.

Reactor building hydrazine spray purps.

9.

Component supports (including snubbers, hangers, anc similar supports) and support structures for all co ;'c nents designed to seismic category I requirectnts 10.

Turbine stop valves.

11.

Main s team block valve (Uni t I only).

12.

Crosstie valves leading to the p'ocess steam l i ra s

13.

Underground cable sys' tem.

14.

Trans fo rne rs.

15.

Induction motors (IE).

16.

Instrument cables.

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17.

Raceway ins talia tions conta ining li c.% l e s and ot'.

raeeway installations whose f aiiure (os ad damage- 'afe:.

related i tems.

18.

Control room smoke detectors and toxic ga. rent tne -

19.

Radiation monitoring (fixed and poetable).

20.

Radioactivity monitoring (fixed and portable).

21.

Radioactivity samplir.g (air, surf aces, liquid,).

22.

Radioactive contamination measureme',t and analysis.

23.

Personnel monitoring internal (e.g., wholt body r.cyn tei and external (e.g., TLD sys tem).

24.

Instrument storage, calibration, and raintenance.

25. Decontamination (facilities, personnel, and equipwnt).

26.

Respiratory protection, including testing.

27.

Contamination control.

28. Accident-related meteorological data collection equipment.
29. Expendable and consumable i tems necessary for the func-tional 9erfonnance of safety-related s tructures, systems,

and components (i.e., weld rod. fuel oil, boric acid, snubber oil, etc. ).

30. Main dike slope adjacent to the emergency cooling water pond.

31.

8affle dike slope adjacent to the energency ccoling water p on d.

32. Pennanent dewatering system.

33.

Emergency water cooling reservoir.

34 Valve operators for all safety-related valves l

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35. Motors for all safety-related pumps.

36.

ECCS pump room ventilation.

37. Measuring and test equipment used for safety-related strur tures, sys tems, and componen ts.

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bl Provide a ceauei tsen t tha t the s a fe ty-re la te d ins t ruren ta t i on o a

controls (I AC) described in Sections 7.1 through 7.6 of the F W j

plus safety-related !&C for safety-related fluid systees wili ! e seject to the pertinent requirements of the FSAR OA progrc

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can be done by another footnote to Table 3.?-1.

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c. of NUREG-0737, " Clarification of IMI Action rien L.or.. M -

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ments" (November 1980) identified numerous i ters tha t are sa f ety-i related pnd appropriate for OL application and therefore shcald t4 cn l

Table 3.2-1.

These items are lis ted below.

Add the apprcpria tr ite s to Table 3.2-1 and provide a comitr.ent that the remaining ite~. are sihject to the C* pro-gram or justify, pertinent requirements of the f5AR operaticr.a) not doing so.

NUREG-0737 (Enclosure 2)

Clarification item

1) Plant-safety-paremeter display console.

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2) Reactor coolant system vents.

II.B.1

3) Plant shielding.

II.B.2

4) Post accident sampling capabilities.

II.B.3

5) Valve position indication.

II.D.3

6) Auxiliary feedvater system.

II.E.1.1

7) Auxiliary fecevater system initiation,and

,l I.E.1. 2 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.

II.T.1 12)

Instrumentation for detection of inadequate II.F.?

core-cooling.

13) Poser supplies for pressurizer relief valves.

II.G.1 block valves, and level indicators.

L 14)

S' fety-grade trip anticipatory.

11.,. 2(10; a

15) Automatic PORY isolattog.

II,y 3:3)

16) Automatic trip of reactor coolant puros.

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17) Emergency plans (and rela te.' e pitr. ent',
18) Equipaent and other i tems associated w t' tr -
  • 1 emergency support f acilities.

19) inplant 1 radia tion moni toring.

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20) Control-room habi tabi li ty.

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