ML20024E852

Opines That Transamerica Delaval,Inc Should Make 10CFR21 Notification That Diesel Generator Exhaust & Intake Sys Are Not safety-related

ML20024E852
Person / Time
Site:	05000000, Midland
Issue date:	08/10/1983
From:	Cook R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20024E849	List: ML20024E848 ML20024E852 ML20024E855 ML20024E857 ML20024E866
References
NUDOCS 8309070136
Download: ML20024E852 (4)

Text

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• • %qk UNITED STATES

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g NUCLEAR REGULATORY COMMISSION g

a REGION lli S,

799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 80137

'+,*****o August 10, 1983 MEMORANDUM FOR:

J. J. Harrison, Chief, Office of Special Cases, Section 2 FROM:

R. J. Cook, Senior Resident Inspector, Midland Site

SUBJECT:

MIDLAND DIESEL GENERATOR EXHAUST SILENCERS Consumers Power Company supplied additional information responding to an item of noncompliance identified in NRC Inspection Report 50-329/82-22; 50-330/82-22 (Item 82-22-08) by letter to Mr. J. G. Keppler, Regional Administrator dated July 12, 1983.

In this response (ltr dtd July 12, 1983) Consumers Power Company stated that, "fDI (Transamerica Delaval, Inc.) has stated that they had not pre-viously provided safety-related exhaust silencers to others, and did not consider the silencers to perform an active safety-related function." This sentence was discussed on July 29, 1983 at the ASLB Hearings. I responded to Board question-ing by stating that perhaps Transamerica Delaval, Inc.

should have made a 10 CFR 50 Part 21 notification when it was established that non-safety-related silencers were supplied.

The Headquarters Daily Report for July 28, 1983 (copy attached) states that a Part 21 notification had been made by Gilbert Associates pertaining to the diesel generators at the Perry Nuclear Power Station and the ability of the exha.1st system as designed to elevate the engine back pressure. A telecommunication with the Resident Inspector Office at the Perry Plant revealed that Perry uses Transamerica Delaval, Inc. diesel generators.

The Part 21 notification by Gilbert Asscciates at the Perry Plant adds credence to my belief that Transamerica Delaval, Inc. should make a Part 21 notification pertaining to diesel generator exhaust and intake systems not being safety-related.

(reference CPCo NCR M01-9-3-158 and FSAR Table 3.2-1 attached)

W R. J. Cook Senior Resident Inspector Midland Site cc/ attachments B. L. Burgess 8309070136 830831 DR ADOCK 05000329 AUG.151983

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e MIDLAND I&2-FSAR TABLE 3.2-1 (continued)

Design FSAR Quality Code /

Seismic System / Component Section Location Group Standard Category Engine driven G

D DEMA I

30 jacket water pump Piping and valves 15 Engine mounted

• G NA DEMA I

27 Non-engine mounted 0,G C

III-3 I

30 Diesel Generator 9.5.6 Starting System Air receivers G

C III-3 I

Compressors G

NA NA NA Air dryers G

NA NA NA l15 Piping and valves Air receiver to engine G

C III-3 I

compressor to receiver G

D B31.1 NA 15 Engine mounted G

NA DEMA I

Filters G

NA NA I

Diesel Generator 9.5.7 Lubrication System Lube oil cooler G

C III-3 I

Lube oil sump G

C III-3 I

tank 30 Auxiliary Jube G

C III-3 I

oil pump Engine driven lube G

D DEMA I

oil pump Lube oil keepwarm G

C III-3 I

l30 i

pump Piping and valves Engine mounted G

NA DEMA I

l15 Aux skid mounted G

C III-3 I

Diesel Generator 9.5.8 Combustion Air Intake and Exhaust System Turbocharger G

NA DEMA I

Intake air louvers G

NA NA I

(sheet 35) l Revision 34 l

6/81 i

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MIDLAND I62-FSAH TABLE 3.2-I (continued)

L'esi gn FSAR Quality Code /

Seismic System / Component Section Location Group Standard Category Intake filters G

NA NA I

l15 Ducts and dampers G

NA SMACNA I

Intake and G

NA NA I

exhaust silencers Ch mical Waste 9.5.9 System Motors E,T NA-NEMA MG-1 NA Pumps E,T D

HI NA Piping and valves U,E,T D

B31.1 NA Oily Waste 9.5.10 System Motors E,P,T NA NEMA MG-1 NA Pumps.

E,P,T D

HI NA Piping and valves E,0,T,U,P D/NA B31.1 NA l21 Tanks P

D API-650 NA (sheet 36)

Revision 34 6/81

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NOTE TO:

E. L. Jordan, Director at fite La Division of Engineering and Quality Assurance

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FROM:

Darl Hood, Project Manager Licensing Branch No. 4 Division of Licensing

SUBJECT:

POTENTIAL PART 21 ISSUE REGARDING INTERNAL DIESEL GENERATOR MUFFLER FAILURES A potentia'i Part 21 issue was identified during a hearing session on the i

Midland Plant, July 29, 1983. The issue is whether or not non-seismic mufflers and exhaust systems for diesel generators can fail in a manner which would restrict the exhaust flow path and thereby, adversly impact starting or subsequent operation of the emergency diesel generat'>rs following a seismic event.

Enclosed hearing transcript pages 19535-19537 and James W. Cook's letter of July 12, 1983, describe this concern.

The issue is not restricted to the Midland Plant. Non-seismic mufflers and exhaust systems provided by Transamerica Delavel, Inc. (TDI), to other nuclear plants have not been designed to safety-related requirements.

Because the design is being corrected to be Category I on the Midland Plant, no seismic analyses of exhaust blockage potential has been provided to the NRC during its Midland rt. view.

I also do not know whether the problem applies to plants with diesel generator vendors other than TDI.

o Darl Hood, Project Manager Licensing Branch No. 4 Division of Licensing

Enclosure:

As stated cc: See next page AUG 291983

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CUDGE BECHHOEFER:

Yes, there has been.

The other 2

way around.

3 MS. BERNABEI:

I think it has been that Category 4

1 is always Q.

5 JUDGE BECHHOEFER:

Everything that is Seismic 6

, Category 1 is Q.

7 MS. BERNABEI:

The assumption of this is that Q can be bro' ken down to Category 1 and non-Q.

8 9

MS. LAUER:

If I can ask a preliminary question.

10 BY MS. LAUER:

11 Q

Back of the whole system is Q.

Does that mean 12 every component in the system is necessarily Q?

13 A

First off, I do not know if it says that the whole 1d system is Q, to be honest with you.

I cannot answer that 15 question without having an opportunity to go back and review

~

16 the words in the FSAR.

The thing was, in our prose, we I

17 indicated that -- if I remember right -- that these particular 3

18 portions, pertaining to the muffler system, that that was 3

I 19 required to be safety related, as defined by the FSAR.

Ij 20 MS. LAUER:

No further questions.

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21 BOARD EXAMINATION t

l 22 g

BY JUDGE HARBOUR:

5 23 Q

Referring to Consumers Power Exhibit 51, which g.

24 is tpe letter to Mr. Keppler from Mr. Cook --

25 A

The Jul'y letter, July 12th letter?

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19536

.lb2 1

Q That's right.

Correct.

Section C-2 -- starts 2

on the second page of C-2.

The first sentence,

s. tarting with 3

TDI, which stands for TransAmerica DeLaval.

Do you see that d

sentence there?

5 A

Yes.

I see s,everal starting with TDI.

At the 6

top you mean?

7 Q

The top of the page.

8 A

Okay.

Yes, sir.

9 0

Are silencers on diesel. generators always Siesmic 10 Category l?

11 A

I feel that they'should be.

I cannot say whether 12 they always are.

The rease,n I feel that way is because it 13 is imperative that the diesel generator be able to function 14 during the earthquake events.

So if any damage could be 15 5

^

sustained by either the intake or the exhaust, it would cripple 16 3

the engine since it would either not put out its required I

17 amount of power or would not run at all, depending.

h, 18 Q

In other words, you believe the diesel generator --

1 E

19 diesel engine on the generator would not run if the maffler was t

t 20 disconnected?

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g 21 A

It would run if the muffler was disconnected.

My r

22 concern would be that the muffler would close off the exhaust

,5 23 or that a portion of the piping would become choked or such 2d that-it would reduce the flow of exhaust gases from the engine.

1 25 The same concern would also apply to the intake side of the t

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19537 ilb3 I

engine.

2 Q

Do you know whether TransAmerica DeLaval has furnished diesel generators to be used at sites in California, d

or a site?

5 A

Yes, they have and I'm trying to think what site 6

.it was.

I want to say Rancho Seco, if I recall right.

When 7

they issue a Part 21 notice, they put the listing of the a

affected plants and if I remember right on one of those

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listings there was a California plant listed., I think it f

9 10 was Rancho Seco, but I do not want to say for,"sure without 1

11 checking.

t 12 Q

To you knowledge, do all sites for' nuclear power 13 plants in California have larger safe shutdown earthquakes id than Michigan?

15 A

5 Yes, to my knowledge.

16 g

Q Do you have any comment, then, on the statement 8*

17 that TransAmerica DeLaval has stated that they have not nj 18 previously provided safety related exhaust silencers to others?

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I personally feel that TransAmerica DeLaval should

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3 issue a Part 21 if that is truly the. case.

r s

l 21 Q

You were asked about the root cause.

From your

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!g 22 description it seemed to me that the fact that the drawing 8

23 y

did not indicate that the muffler should be Seismic Category f

24 1 were limiting to all of the other problems.

No matter what 25 anybody did, if they referred back to the basic drawing and it e,. ~, -.. -......,.....

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_. AJ General o ffices: 1945 West Parnell Road, Jackson, MI 49201. (517) 78a o453 July 12, 1983 go. 3sq 50 33c>

Mr J G Keppler, Regional Administrator US Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND ENERGY CENTER DOCKET NO 50-329 AND 50-330 - AMENDED MIDLAND PROJECT RESPONSE TO NRC, REGION III LETTER DATED MAY 23, 1983 File: 0485.16 UFI: 42*05*22*04 Serial:

CSC-6781 0.4.2 70*01

REFERENCES:

(1) J W Cook letter to J G Keppler, dated June 24, 1983, Serial CSC-6764 (2) J G Keppler letter to J W Cook, dated May 23, 1983 This. letter, including Attachment 1, and in addition to Reference 1, provides our amended response to Reference 2.

We appreciate your consideration in extending the due date for this response in order that our personnel could properly examine the vendor information available and hopefully provide a thorough and accurate response. This was discussed w'th your Mr. R. Cook.

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JWC/ BHP /kim cc: RFWarnick, NRC Region III JJHarrison, NRC Region III RNGardner, NRC Region III RJCook, NRC Senior Resident Inspector, Midland Site RBlandsmin, NRC Region III~

BLBurgess, NRC Resident Inspector, Midland Site O

S)U2 01983 Oj kl OC0783-0004A*CN01,

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CONSUMERS POWER COMPANY Midland Units 1 and 2 Docket No 50-329/50-330 1.etter Serial CSC-6781 Dated July 12, 1983 At the request of the Commission and pursuant to the Atomic Energy Act of

• 1954, and the Energy Reorganization Act of 1974, as amended and the Commission's Rules and Regulations thereunder, Consumers Power Company submits the amended response to J G Keppler letter to J W Cook dated May 23, 1983.

CONSUMERS POWER COMPANY By

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. Cook, Vice President Proi/J ets, Engineering and Construction 7

Swornandsubscribedbeforemeth3/

ay of d,. /98, f

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Notary Public My Commission Expires S -Y-[b PATRICIA A. PUFFER Notary Public. Bay County, Mt My Commissien Expires Mar. 4,1986 I

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OC0783-0004A-CN01 i

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Amended Response to J G Keppler letter to J W Cook dated May 23, 1983 The amended response to J G Keppler letter to J W Cook dated May 23, 1983 is submitt'ed in the following format:

,NOV Item B Identification Number A.

Statement of Original Violation (from J G Keppler letter to J D Selby dated February 8, 1983: Notice of Violation EA 83-3.)

3.

Request For Additional Information (from J G Keppler letter to J W Cook dated May 23, 1983.)

C.

Statement of Additional Information 1.

Admission or denial of the alleged violation 2.

The reasons for the violation, if admitted 3.

The corrective steps which have been taken and the results achieved 4.

The corrective steps which will be taken to avoid futher violations 5.

The date when full compliance will be achieved t-h e

• 4 OC0783-0004A-CN01

c OL/0M SERVICE LIST Mr Charles Bechhoefer Esq Mr Frank J Kelley, Esq Administrative Judge Attorney General of the Atomic Safety & Licensing Board Panel State of Michigan U S Nuclear Regulatory Commission Mr Stewart H Freeman, Esq Washington, DC 20555 Assistant Attorney General Environmental Protection Div 720 Law Building Lansing, MI 48913 Dr Frederick P Cowan Mr Myron M Cherry, Esq Administrative Judge Cherry & Flynn 6152 N Verde Trail 3 First National Plaza Apt B-125 Suite 3700 Boca Raton, FL 33433 Chicago, IL 60602 Mr Michael Miller, Esq Mr Wendell H Marshall IsF2m, Lincoln & Beale RFD 10 3 First National Plaza Midland, MI 48640 Suite 5200 Chicago, IL 60602 Mr D F Judd, Sr Project Manager Mr John Demeester The Babcock & Wilcox Company Dow Chemical Buf1 ding P O Box 1260 Michigan Division Lynchburg, VA 24505 Midland, MI 48640 Atomic Safety & Licensing Board Panel Ms Mary Sinclair U S Nuclear Regulatory Commission 5711 Summerset Street Washington, DC 20555 Midland, MI 48640 Atomic Safety & Licensing Board Panel Mr Steve Gadler U S Nuclear Regulatory Commission 2120 Cart'er Avenue Washington, DC 20555 St Paul, MN 55108 Mr William D Paton, Esq Mr Lee L Bishop Counsel for NRC Staff Harmon & Weiss U S Nuclear Regulatory Commission 1725 I Street, NW #506 Washington, DC 20555 Washington, DC 20006 Ms Barbara Stamiris Mr C R Stephens 5795 North River Road Docketing and Service Station Route 3 Office of the Secretary Freeland, MI

• ,8623 U S Nuclear Regulatory 4

Washington, DC 20555 Dr Jerry Harbour Lynne Bernabei U S Nuclear Regulatory Commission Governmental Accountability Atomic Safety & Licensing Board Panel Project (GAP)

Washington, DC 20555 1901 Q Street NW Washington, DC 20009 OC0783-0004A-CN01

.?

p NOV Item B - 2.a (82-22-08)

A.

Statement of Original Violation

" Measures were not estchlished for the selection and review for suit-ability of application of "Q" materials associated with the diesel gener-ator exhaust muffler in that design drawings and specifications did not indicate the material identity of the installed muffler saddle supports and plates."

5.

Request For Additional Information "Regarding Item B.2.a. we reiterate our position that the lack of design documentation which specified the material requirements for the diesel generator exhaust mufflers constituted an item of noncompliance. Please provide any additional information supplied by the vendor regarding the traceability of the exhaust muffler materials, and as appropriate, your corrective actions and the results achieved, corrective actions taken to 1

avoid further noncompliance, and the date when full compliance will be achieved."

C.

Statement of Additional Information

'l I

1.

The violation is admitted.

2.

The violation occurred because the design intent was not implemented in the design, fabrication and inspection of the exhaust silencers by the diesel generator prime supplier, Trans' america Delavel, Inc.,

(TDI). This was not recognized or corrected by the design organiza-l tion responsible for the pro'urement. The design intent was that the c

l diesel generator exhaust silencers be subject to the appropriate elements of 10CFR50, Appendix B, and ANSI N45.2-1971.

Tne Bechtel procurement documents for the diesel generators specify the functional performance requirements of the diesel generators.

It is not the intent to specify all details of design and construction.

The expertise for the der. ailed design and construction of the diesel generator and accessories rests with TDI.

The procurement documents (Specification 7220-H-18 Paragraph 12.2) specified; " Quality assurance requirements are applicable to all components and assemblies which affect the reliability and ability of the equipment furnished by the Seller to perform its design function."

Additionally, the specification p'rovides a check of this requirement by requiring the vendor to submit a list of all items which he intends to sup' ply as "Q" for review by Bechtel. When properly implemented, these requirements in Specification 7220-M-18 provide adequate direc-tion to the vendor and control by Bechtel. Bechtel did not take action to correct the failure of TDI to fully comply with the require-ments of Specification 7220-M-18, Paragraph 12.3 to submit a " list of all items to be furnished to quality control standards."

OC0783-0004A-CN01

~._

j TDI has stated that they had not previously provided safety-related exhaust silencers to others, and did not consider the silencers to perform an active safety-related function.

Specification requirements were not understood by TDI to apply to the exhaust silencers. As a i

result, the exhaust silencers were not included as an item to be safety-related. TDI procured the exhaust silencers from a sub-supplier, American Air Filter (AAF), with essentially commercial quality standards. TDI did specify to AAF that material cert-ification, weld procedures, and weld procedure qualifications be provided. AAF did not fully comply with the purchase order require-ments of TDI.- TDI did provide a seismic analysis of the exhaust silencers to verify the capability to withstand a safe shutdown earthquake.

The procurement documents leave the' selection of materials for cons-truction of the exhaust silencers to TDI and AAF. The materials of construction were selected by AAF and specified in the fabrication drawing based on its experience. Common grades of steel (e.g., A-36 and A-569) are typically used.

TDNprovidedacertificateofconformancetothepurchaserequirements for the exhaust silencers and the saddle suppport modification plates as required by the procurement documents. That information is on site.

If the exhaust silencers and saddle support modification plates had been identified by TDI as having a safety-related function, they would have been included under the TDI quality assurance program.

i i

That program would have required actions to be taken to assure approp-riate material identification and control. Specific material trace-l ability (i.e., certified material test reports) is not applicable because of the design and function of these items.

3.

The following corrective action for the exhaust silencers has been taken: We have met with TDI and. visited AAF, and subsuppliers at their facilities, and reviewed all available purchasing and quality documentation. TDI will provide a Material Certificate of Compliance to confirm that the materials used were consistent with the seismic analysis. TDI has been directed to provide a fabrication inspection procedure to verify that construction of the exhaust silencer satis-fies the design and seismic analysis. This inspection will be per-formad on site under the direction of MPQAD.

If any deficiencies are found during the inspection, the silencers will be reworked to conform to the requirements.

In accordance with the partial redisposition of NCRs 4693 and 4994, muffler saddle support end and center support plate extensions are to be replaced because the dimensions of the slots / holes do not conform to the design drawings.

Replacement plates will have material car-tificates of compliance.

Project Engineering and TDI have reviewed the technical specifications to determine if other items have been considered to be non-safety related contrary to the design intent. To date, the intake air l

j OC0783-0004A-CN01 L

~

filters, intake air silencers, intake air flexible connectors, and exhaust expansion joints have been identified as not being considered safety related by TDI, and consequently not provided as safety related. An action plan to upgrade these items to safety-related-status by verifying that the construction of these items satisfies the design and seismic analysis is underway. NCRs M-01-9-3-158 and 4955 have been written to document the indeterminant status of these components.

1.

Further investigation to ascertain if there are any additional suspect items in the package provided by TDI is in progress and is expected to be complete by August 15, 1983.

4.

The general approach to ensure that purchased material / equipment is fabricated in accordance with the specification requirements is as follows: The Project Engineering review and acceptance of vendor submitted documents required by the specification such as drawings, procedures, and quality assurance manual; the Procurement Supplier Quality Department's performance of audits on adequacy of vendor quality program implementation and source surveillance inspections at the vendor's facility as required by the purchase order; the QC performance of receipt inspection to verify supplier submittal of the required documentation on "Q" items that are received on site; the Supplier Quality Review of the required documentation for adequacy; and MPQAD/QA performance of a quality overview inspection on selected items on site, j

In view of the experiences on this procurement, we will conduct a i

review of functional / performance oriented procurements which contain "Q" and non "Q" items to verify that safety-related items were desig-l nated by the vendors in accordance with project design requirements.

j A review program and schedule will be developed by September 10, 1983..

5.

Full compliance will be achieved when:

a) Receipt of the exhaust silencer Material Certificate of Compliance and completion of the fabrication inspection is expected by October 15, 1983. A schedule for any subsequent rework as a result of the inspection will be established at that time, b) The exhaust silencer saddle support and center support plate extensions are replaced and NCRs 4693 and 4994 are dispositioned, c) NCRs M-01-9-3-158 and 4955 will be resolved by October 15, 1983.

A, schedule for any subsequent rework resulting from this resolu-tion will be established then.

d) Further investigation to ascertain if there are any additional l

suspect items in the package provided by TDI is expected to be complete by August 15, 1983.

l OC0783-0004A-CN01 1

~

i e) The review program subsequent review i and schedule describ s

completed and any fi din part 4 an ed n ings the are addressed.

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OC0783-0004A-CN01 t

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BCC W R Bird P14-418A J E Brunner, M1079 F W Buckman, P14-113A D M Budzik, P124-517 M L Curland, MPQAD M A Dietrich, Bechtel F D Field, Union Electric J F Firlit, JSC236A W J Friedrich, MPQAD/QC W D Greenwell, Bechtel AA G A Hierzer, Bechtel R C Hollar, Bechtel AA E M Hughes, Bechtel AA K E Marbaugh, QA-NO, Midland B W Marguglio, JSC220A D B Miller, Site Manager (3)

NRC Correspondence File F24-517 J A Rutgers, Bechtel AA P Steptoe, IL & B, Chicago R A Wells, MPQAD F C Williams, IL & B, Washington t.

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NONCONFORMANCEREPOYf"PL'

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MAY l 3 B 3 M01-9-3-158

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C. P. Co. Ix del '"' " ""' '"

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N/A Q[tagad May 12, 1983

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12. LOCAT Om 23 FIAN :

13.

3AIE OF REVISION:

• ~ ~..~;~ 7.. e s e Bechtel Project Diesel Generator 22-

• * * * ^

Engineering Building N/A I

usunuc7 Midland Plant FSAR, Section 9.5.8.3 and Table 3.2-1 requires the "

36.

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.'.[* ' g y Hughes _ Djesel Generator intake. (combustion air) and exhaust systems includ-f,g,, c cy, W-ing silencers, turbochargers, filters, ducts, dampers and louvers to l s 'I ' P(-

be designed in accordance with Seismic Category 1 requirements.

pggggy,f JAMooney (continued )

.1.5-##.er EHFeck son:CarCamCz:

it.

Jo.~c:.

JARutgers Contrary to the above, only the unsupported shell (not including m.rlane TKSubramariac internal components) of the silencers have received a seismic C

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analysis, 6.

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X (1) Bechtel to instruct vendor (Transaperica Delaval Inc) to

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re-design all above components, in their entirety, in accordance 6g-i"-

X with the above noted project commitments.

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PHOJL C15. E NGIN E E7.IN G AND CONSTRUCTION-

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NONCONFORMANCE REPORT Power na :xx:Ar. rno:MM.,., - 58 j EU*f"I PROCESS Con RECTIVE ACTIC. N

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1.

Specification not sufficiently clear.

1 2.

Failure of vendor'to make inquiry as to components requiring S__eismic 1 ces,un.

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ACN42. ROOT CAUIE($), IF 5277TJIZX7 paM ABoVE (20 E COMr".ZE FI QRG. G:3PONSIBM FOR DCK333 CA):

FROCESS CA RE'II@ TRQM:

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X rAsar:AM2 MOCUMM7 DEFICUM aussa en uconax a rom naCz3s CA:

.1.

B::chtel is to review documentation relating to all diesel generator components -

required to be seismically qualified by the FSAR/ Specification to ensure that all components supplied by this vendor or his supplier's comply with these requirements.

2.

MPQAD is to receive the above documentation for review and concurrence.

l MOCISS CA TD E TA.D IT OR3($) CECFZD IN BIDCE 4 & LA E CT CC+G".2723:

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.o NCR # M01-9-3-158 Fagn 3 or 3 Block 16 (continued ):

Specification 7220-M-18(Q), R. 8; Appendix A - Design Data for Emergency Diesel Generators.

Article 2.1 states in part ".

the Emergency Diesel Generators and their auxiliaries are designated Seismic Category 1 and shall be designed..

Block 18 (contitaued ):

2.

If the existing, installed components are deemed by the vendor as acceptable without removal, the vendor is to submit to Bechtel documentary justifica-

~

tion for this action.

3 If the existing components do not meet Seismic Category 1 Criteria, vendor is to replace them with acceptable components.

4.

MPQAD is to review and concur on Corrective Action Items 1 through 3 above.

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ISHAM, LINCOLN & BEALE cr.,

%g COUNSELORS AT LAW ThatE FRST NATIONAL M CMrCAGO. ILuMOis tomat TELEPHONf 3t2550300 waswsNGTON OFFICE D

1872 W TELDL153B8 1100 CONNE AVENut N W wituAM G1EALE. ions te23 wASMiNGTON D C 20c36 August 12, 1983 sat uma UNITED STATES OF AMERICA FRf NCIPAL STAFF NUCLEAR REGULATORY COMMISSION RA v/f,.

ENF D/RA SCS h BEFORE THE ATOMIC SAFETY AND LICENSING BOARD A/RA

.A0G DPRP Sto.

f DR'tA_

RC //

In the Matter of:

)

Docket Nos. 50-329 OM DRi45F

)

50-330 OM DE CONSUMERS POWER COMPANY

)

Docket Nos. 50-329 OL ML (Midland Plant, Units 1 & 2)

)

50-330 OL OL F LE p 'EK /

4 Dr. Frederick P. Cowan 6152 North Verde Trail Apt. #B-125 Boca Raton, Florida 33433 Dr. Jerry Harbour Charles Bechhoefer, Esq.

Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission East-West Towers East-West Towers Room E-454 Room E-413 4 350 East-West Highway 4350 East-West Highway Bethesda, Maryland 20014 Bethesda, Maryland 20014

Dear Administrative Judges:

At the last hearing session, Judge Harbour re-quested that Consumers Power determine the date as of which the FSAR specified that the diesel generator exhaust system should be Seismic Category I.

This letter and the accom-panying attachments are intended to respond to that inquiry.

Mr. Bruce Peck testified that Bechtel issued the

_specifications to Transamerica DeLavel, Inc. ("TDI") for the procurement of the diesel generator system in approximately May of 1977.

(Transcript at 19563).

At that time the FSAR had not yet been issued and the governing document was the gea88)h AUG 221983 f

G

.m,'~~._.

L'

d Dr. Jerry Harbour Charles Bechhoefer, Esq.

Dr. Frederick P. Cowan August 12, 1983

' Page Two PSAR.

Appendix 5A of the PSAR lists the emergency gen-erators as a Class 1 system.

The PSAR further states that

"[w] hen a system as a whole is referred to as class 1, portions not associated with loss of function of the system are designated as Class 2."

(Attachment A includes the relevant pages of the PSAR).

The design criteria for Class 1 and Class 2 systems and equipment set forth in PSAR Ap-pendix 5A do not refer specifically to Q-ness.

However, the procurement documents supplied to TDI specified that "[q]uality asstrance requirements are applicable to all components and assemblies which affect the reliability and ability of the equipment furnished to the Seller to perform its design function."

(C.P.Co. Exhibit 51).

The FSAR was submitted to the Midland docket in November of 1977.

Attachment B to this letter includes a portion of FSAR section 9.5.8, " Diesel Generator Combustion Air Intake and Exhaust System."

Revisions to the original FSAR are noted in the right hand margin of the pages with a vertical line marking the portion revised and an accom-panying number indicating the revision which incorporated the change.

The pages included herein indicate that the diesel generator exhaust system was to be designed in ac-cordance with Seismic Category I requirements (59.5.8.3) and that codes and standards indicated in Table 3.2-1 should be applied to the exhaust system (59.5.8.1.3).

These require-ments have been a,part of the FSAR since November of 1977.

(

As Attachment C to this letter, I have provided l

relevant portions of FSAR section 3.2, " Classification of Structures, Components, and Systems," including pages from Table 3.2-1 referred to above.

Table 3.2-1 lists the diesel generator intake and exhaust silencers as Seismic Category I and provides that design requirements were to be specified by the designer "with appropriate consideration of the intended service and operation conditions."

These require-ments have also been a part of the FSAR since November of 1977.

In order to provide greater clarity and more de-tail, the Project Q-list was revised in May of 1983.

This i

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~

Dr. Jerry Harbour Charles Bechhoefer, Esq.

Dr. Frederick P. Cowan

' August 12, 1983 Page Two Revision 10 breaks down components of the diesel generator system and now lists the exhaust silencers specifically as Q items.

(Attachment D provides the relevant portions of the current Q-List).

At the time when the diesel generators were ordered, Revision 7 to the Q-list did,not provide this level of detail.

(See Attachment E).

The appropriate use of the categorizations Seismic Category I and Q-listed is further clarified in Consumers Powers' response to DGB Notice of Violation Item B-2e which states that structures, systems, or components identified as Seismic Category I are considered Q and project QA program requirements are to be applied to them.

A review was per-formed to confirm that where the Seismic Category I desig-nation was applied to structures, systems, or components QA program requirements had been applied.

(See Attachment 1 to B. Peck testimony following Tr. 18921 at p. A2-24).

very truly yours,

~

l Rebecca J. Lauer One of the Attorneys for CONSUMERS POWER COMPANY RJL:bc Encs.

t cc:

Midland Service List (w/encs) l

- s l

l

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t 1

e, ATTACHMENT "A" APPENDIX 5A TESIGN PASES FOR STRU7TURES, SYSTE'G A!!D EQUIPIG::T -

. GENERAL The design bases for structures for normal operating conditions are governed by the appii nble building design codes. The design bases for specific systems and equip' tent are stated in the appropriate PSAR Section. The basic design cri.erion for the maxi =u: loss-of-coolant accident and cei:=ic condi-4 tions is that there be no less of function if that function is related to public safety.

CLASSES OF STRUCTURES, SYSTE'G AUD EQUIPI'ENT CLASS 1 Class 1 structures, systems and ecuipment are those whose failure could cause release of radioactivity which would exceed 10 CFR 20 li=its at the site bound-ary or those essential for 1 =ediate and long-ter= operaticn following a loss-of-coolant accident or those necessary for safe shutdown. When a system as a whole is referred to as Class 1, portions not associated with loss of function of the syste= are designated as Class 2. '

The following are typical Class 1 structures:

Reactor buildin63.

Portions of the auxiliary building housing the engineered safeguards systems, centrol room and radioactive caterials.

Enclosures for the service water pu=ps, auxiliary feed-vater pu=ps and diesel generators.

Diesel fuel storage facilities.

Supports for Class 1 system co=ponents.

Typical Class 1 equipment and systems follow:

Reactor vessel and internals including control rods and control rod drives.

Other reactor coolant system components (steam generators, pressur-iter, pu=ps, etc) and piping, including vent and drain piping inside the reactor building.

2 Reactor building penetrations up to and including the first isola-tion valve outside the reactor building.

Main steam and main feed-water piping up to the first stop valves outside the reactor building.

-s 5A-1 A.cndment No. 6 12/26/69

Nw and spent fuel storace racks and fael nar.dling equip. tent, in-ciuding the crane above the fuel pool (unloaded condition).

Motor-driven and steam-driven auxiliary feed-water systems.

Emergency generators including fuel supply..

Reactor building crane (unloaded condition).

Control boards, switchgear, load centers, batteries, transformers, and cable runs serving Class 1 equip =ent.

Service water systems (critical portions).

Cn=penent cooling (critical portions).

Reactor building spray system.

Reactor building air recirculation and cooling system.

Icu-pressure injection and decay heat removal system.

I'.skeup and purification system (critical portions).

Core flooding tanks and piping.

Borated water storage tank.

CIASS 2 Class 2 structures, systems and equipment are those whose failure vould not result in the release of radioactivity which would exceed 10 CFR 20 limits at Ithesiteboundaryandwouldnotpreventsafeshutdown. The failure of Class 2 structures, systems and equip =ent nay interrupt power generation.

DESIGN PASES CIASS 1 STRUCTURES DESIGN Normal Operation - 7br loads to be encountered during normal plant operation (excluding earthquake loads), Class 1 structures are designed in accordnuce with design methods of accepted standards and codes insofar as they are applicable.

(ParagraphDeleted)

Ehe final design of Class 1 concrete stnactures (except the reactor building) under nor=al operating conditions satisfies the most severe of the following load co=bination equations. (Design equations for the reactor building are given in Section 5, Reactor Building and Structures.)

i 5A-2 A:endment No. 6 12/26/69

. ::=-

=

. =.

p = 0.65 for tension, shear, bond, and anchtrage Ir. reinforcel concrete.

p = 0.75 for spirally reinforced concrete compression mezbers.

d = 0 70 for tied compression me=bers.

~

$ = 0 90 for fabricated structural steel.

( = 0 90 for reinforcing steel (not prestressed) in direct tension.

p = 0.85 for lap splices of reinforcing steel.

p = 0 90 for velded or mechanical splices of reinforcing steel, p = 0 95 for prestressed tendons in direct tension.

The reactor building, engineered safeguards, steam and feed-water system components are protected by barriers from all credible missiles which might be generated from the reactor coolant systen. Local yielding or erosion of barriers is permissible due to jet or missile i= pact, provided there is no general failure.

The final design of the missile barrier an'd equipment support structures inside the reactor building is reviewed to assure that they can withstand applicable pressure loads, jet forces, pipe reactions and earthquake loads without loss of function. The deflections or deformations of structures and supports are checked to assure that the functions of the reactor building and engineered safeguards equip =ent are not impaired.

CLASS 1 SYSTES AND EQUIPMEI;T DESIGN C::ponents and systems classified as Class 1 are designed in accordance with i

the following criteria:

Primary steady state stresses when ce=bined with the seismic a.

stress resulting from the " Design Earthquake" are maintained within the allovable working stress limits accepted as good i

practice as set forth in the appropriate design standards, I

eg, ASME Boiler and Pressure Vessel Code, UASAS B317 Code for Pressure Piping.

b.

Primary steady state stress when combined with the seismic stresses resulting from the " Maximum Earthquake" are limited so that the function of the co=ponent or system is not so im-paired as to prevent s safe and orderly shutdown of the plant.

CLASS 2 STRUCTURES DESIGN Class 2 structures are designed in accordance with design methods of accepted cedes and standards insofar as they are applicable. Seismic design is in t

SA-5 Amendment No 5 11/3/69 i

r accernance with the Uniform Building Code witit the apprvpriate -wd.im

'.m.

allowance and shear coefficients.

CIASS 2 SYFC'S A?ID EQUI?!EI.T DESIGN

. Class 2 syste s and equipment are designed in accordance with design :.ethods "of accepted codes and standards. Wind loads and seis=ic loads, where appli-cable, confere to the require =ents o' :;he Unifem Building Code.

VIIID Ai!D F.GTFOUAEE IDDS FOR CIdSS 1..TRUCTURES WIND FORCE Class 1 si;ructures (except the enclosure over the fuel storage facilities) are designed to resist the effects of a tornado.

The reactor building is analyzed for tornado leading (not coincident with accident or earthquake) on the following basis:

Differential bursting pressure between the inside and outside of a.

the reactor building is assumed to be three pounds per square inch positive pressure.

b.

Lateral force is assu=ed as the, force caused by a tornado funnel l

having a maximum peripheral tangential velocity of 300 =ph and a l

forward progression of 60 mph. These components are conservatively applied as a 300 mph wind over the entire surface of the structure for each reactor building and are additive for a 360 mph wind over the entire surface of other Class 1 stmetures. The applicable por-tions of vind design methods described in ASCE Paper 3269 are used, particularly for shape factors. The provisions for gust factors and variation of wind velocity with height are not applied.

Tornado driven missiles equivalent to an airborne 4 inch by 12 c.

inch by 12 foot plank traveling end-on at 300 mph, or a 4000 pound automobile flying through the air at 50 mph and at not = ore than 25 feet above the ground, are assumed.

l SEISMIC FORCES (E AND E')

AEC Publication TID 7024, " Nuclear Reactors and Earthquakes," is used as l

the basic design guide for seismic analysis.

The " Design Earthquake" used for this plant is a ground acceleration of 0.06 g horizontally and 0.04 g vertically, acting si:aultaneously. The "Naxi=um Earthquake" is a Ground acceleration 0.12 g hori:entally and l

0.08 g vertically, acting simultaneously.

Seismic loads on structures, systems and equip =ent are determined by realis-tic evaluation of dynamic properties and the accelerations obtained from the attached acceleration spectrum curves. (Figures 5-A-1 and 5-A-2 in this Appendix)

~

-s 5A-6 Anendnent No. 8 i

2/9/70 t

I

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MIDLAND 1&2-FSAR ATTACHMENT "B" 9.5.7.4 Tests and Inspections Testing of the diesel generator system is discussed gener, ally in Subsection 8.3.1.1.3.

Abstracts of the diesel generator. system ar's provided in Chapter 14.

The diesel generator lubrica' tion system is operationally tested during the startup and periodic check-out of the diesel generator.

Lube oil pressure and temperature are monitored to ensure operability of the engine driven pump and the recirculation lines.

Operation of the electric pump and heater are evidence of their operability.

Inspection and testing of the system can be performed without disturbing normal plant operations.

The oil is checked periodically to determine that it is within the engine manufacturer's specifications.

The duplex filters and strainers are valved for full flow through one side only and may be removed and inspected for the buildup of impurities following engine operation.

Periodic testing of the diesel generator is discussed in Chapter 16.

9.5.7.5 Instrumentation Applications Instrumentation providEd for the diesel generator lubrication indicators, system includes pressure and temperature switches, and automatic protection devices.

The temperature and pressure

~

switches support the automatic control modes of lubrication Diesel generator controls and indication are provided operation.

at the local diesel generator control panels and in the control room.

These controls, instruments, and annunciators are discussed in subsection 8.3.1.1.3.

In addition, a dipstick is provided on the engine oil sump.

Low lube oil level is the primary means provided for lube oil leakage detection.

A 10 secondary means of detection is provided by the diesel generator room sumps which are equiped with high level alarms as shown on No lube oil sump high level alarm is provided.

l Figure 9.5-30.

DIESEL GENERATOR COMBUSTION AIR INTAKE AND E:CuUST SYSTEM 9.5.8 This subsection discusses the mechanical features of the diesel The standby generator combustion air intake and exhaust system.

power supply (i.e., the diesel generator system) is discussed in detail in Subsection 8.3.1.1.3.

The diesel generator building ventilation system is discussed in Subsection 9.4.7.

9 5.8.1 Design Bases criteria for the selection of design bases are stated in Subsection 1.1.2.2.

Protection of the diesel generator combustion air intake and exhaust system from wind and tornado effects is discussed in Missile Section 3.3.

Flood design is discussed in Section 3.4.

Revision 10 9.5-29 6/78

MIDLAND 1&2-FSAR protection is discussed in Section 3.5.

Protection against dynamic effects associated with postulated rupture of piping is discussed in Section 3.6.

Environmental design is discussed in Section 3.11.

9.5.8.1.1 Safety Design Bases SAFETY DESIGN BASIS ONE - The diesel generator combustion air intake and exhaust systems are capable of supplying adequate combustion g.ir and disposing of resultant exhaust products to permit continuous operation of each diesel generator under a load of 110% of rated load.

SAFETY DESIGN BASIS TWO - The diesel generator combustion air intake and exhaust systems are designed to remain functional during and after a design basis earthquake.

SAFETY DESIGN BASIS THREE - The diesel generator combustion air intake and exhaust systems are designed so that a single failure of any component, assuming a loss of offsite power, cannot result in loss of both diesel generators.

SAFETY DESIGN BASIS FOUR The diesel generator combustion air intake and exhaust systems are capable of being tested even during operation of the diesel generators in accordance with 10 CFR 50 General Design Criterion 10.

9.5.8.1.2 Power Generation Design Bases The diesel generator combustion air intake and exhaust system has no power generation design bases.

9.5.8.1.3 Codes and Standards Codes and standards applicable to the diesel generator combustion air intake and exhaust system are listed in Table 3.2-1.

l 9.5.8.2

System Description

i 9.5.8.2.1 General Description l

l Each diesel generator is provided with an air intake and exhaust system.

The system is shown in Figure 1.2-27.

Major components of the system include intake filters, intake and exhaust l

silencers, and two turbochargers with aftercoolers for each i

diesel generator unit.

A more detailed description of components to is included in Table 9.5-7.

Performance data for the aftercooler heat exchangers are provided in Table 9.5-10.

l N

Revision 10

~

t 9.5-30 6/78

MIDLAND 1&2-FSAR 9.5.8.3 Safety Evaluation Safety evaluations are numbered to correspond to the safety design bases.

SAFETY EVALUATION ONE - The' combustion air intake provides enough

_ air to the turbochargers to ensure rated diesel output un' der the most adverse conditions.

- SAFETY EVALUATION TWO - The diesel intake and exhaust system is designed in accordance with Seismic Category I requirements as specified in Section 3.2.

Systems, equipment, or structures whose failure could result in loss of a required function of the diesel generator intake and exhaust system are checked to determine that they will not fail when subjected to seismic loadings.

SAFETY EVALUATION THREE - The diesel generator air intake is sized to provide adequate combustion air as described in safety evaluation one above.

A single failure of the air intake or exhaust may be assessed as a failure of the diesel generator with which the failure is associated.

In such a circumstance, safe shutdown is attained and maintained by,the appropriate redundant diesel generator installation.

SAFETY EVALUATION FOUR - All active components are capable of being tested during power generation to ensure proper functioning of the system as discussed in Subsection 9.5.8.4 below.

9.5.8.4 Tests and Inspection Testing of the diesel generator system is discussed generally in Subsection 8.3.1.1.3.

Abstracts of the diesel generator system are provided in Chapter 14.

Visual inspections, pressure and leak testing, and operational checks of the combustion air intake and exhaust system are performed as the system is installed.

The diesel generator combustion air intake and exhaust system is operationally checked during the periodic testing of the diesel generator system.

Periodic testing of the diesel generator is I

discussed in Chapter 16.

9.5.8.5 Instrumentation Application l

l Diesel generator controls and indication are provided at the local diesel generator control panels and in the control room.

l The local diesel generator control panels are mounted on the 27 diesel generator building foundation, which is structurally isolated from the diesel generator pedestals.

The controls, Instruments, and annunicators, associated with the diesel generators are discussed in Subsection 8.3.1.1.3.

l Revision 27 3/80 9.5-31, 1

=

s.

+.

nIDL7.nD 162-FSLR ATTACHMENT "C" 6

3.2 CLASSITICATIOM OF STRUCTURES, COMPCNI!1TS, AND SYf.TEttS This section provides a guide to the classification method of structures, components, and systems.

Subsection -3.2.1 applies to the balance of plant; that is, all structures, components, and systems except those provided by the NSSS supplier.

Subsection 3.2.2 applies to all components and systems provided by the NSSS supplier.

Subsection 3.2.3 lists effective dates of major codes for components including balance of plant and NSSS supplied items.

3.2.1 CLASSIFICATION OF BALANCE OF PLANT STRUCTURES, COMPONENTS, AND SYSTEMS 3.2.1.1 Seismic Classification General Design Criterion 2 of Appendix A to 10 CFR 50, General Design Criteria for Nuclear Power Plants, and Appendix A to 10 CFR 100, Seismic and Geologic Siting Criteria for Nuclear Power Plants, require that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes.

~

3.2.1.1.1 Definitiens Seismic Category I structures, ecmpenents, and systems are defined in accordance with NRC Regulatory Guide 1.29 as those necessary to assure:

The integrity of the reactor coolant pressure boundary a.

b.

The capability to shut down the reactor and maintain it in a safe shutdown condition c.

The capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR 100

- Seismic Category I structures, components, and systems are designed to withstand the appropriate seismic loads as discussed in Section 3.7 and other applicable loads without loss of function.

Seismic Category I structures are sufficiently isolated or protected from other structures to ensure that their integrity is maintained at all times.

Components (and their supporting structures) which are not Seismic Category I and whose collapse could result in loss of 3.2-1

.'r MIDIAND 162-FSAR required function of Seismic category I structures, equipment, or systems are reviewed to confirm their integrity against collapse when subjected to seismic loading resulting from the safe shutdown earthquake.

~

3.2.1.1.2 classifications

~

Table 3.2-1 provides a listing of structures, components, and systems and identifies those which are seismic category I.

Where only portions of systems are identified as seismic category I on this table, the boundaries of the Seismic category I portions of the system are shown on the piping and instrument diagrams in appropriate sections of this report.

Compliance of the above seismic classifications with NRC Regulatory Guide 1.29 is discussed in Appendix 3A.

l l

3.2.1.2 system Quality Group Classification l

This subsection provides the system quality group classification l

for each fluid or gas system pressure-containing component.

components are classified according to safety-related importance as dictated by service and functional requirements and by the consequences of failure.

The design, f abrication, inspection, and testing requirements fixed for each classification provide the required degree of conservatism in assuring pressure integrity.

3.2.1.2.1 Quality Group Classifications Equipment quality group classifications are indicated in Table 3.2-1.

system quality group classifications and interfaces between classifications in systems with ecmponents of different classifications are indicated on the system piping and instrumentation diagrams which are found in the pertinent sections of this safety analysis report.

The boundaries are designated by a three letter sequence, for example, "HBD." The l

last letter (A, B, C or D) stands for applicable code which corresponds to a quality group in the table, as described in Regulatory Guide 1.26.

Regulatory Guide 1.26 does not apply if the last letter is F, G, H, or J.

~

3.2-2

MIDIAND 152-FSAR -

~

Last Letser of Three Letter Corresponding Group Quality Group t'

A A

B B

~

C C

D D

F NA G

NA H

NA J

NA compliance of quality group classification with NBC Regulatory Guide 1.26 is discussed in Appendix 3A.

~3.2.1.2.2 Code Requirements The code requirements applicable to each quality group i

classification are, identified in Table 3.2-2.

Design code requirements corres' pond to those indicated in Section 50.55a of 10 CFR 50 and NRC Regulatory Guide 1.26, Table 1,.except for quality group D pumps.

The design standard of these pumps is discussed in the footnote of Table 3.2-2.

Codes and applicable addenda for all piping and equipment in the plant are listed in Tables 3.2-3 and 3.2-4.

3.2.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS l

PROVIDED BY THE NSSS SUPPLIER f

A system boundary includes those portions of the system required to accomplish the specified safety function and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure when the safety function is required.

This section identifies the B5W classification method for structures, components, and systems.

It is intended that 1) the seismic classification of structures, systems, and components, and 2) the system quality group classification for pressure-containing components of fluid systems utilize the guidelines set forth in Regulatory Guides 1.29 and 1.26 l

_respectively.

3.2.2.1 Seismic Classification General Design Criterion 2 of Appendix A to 10 CFR 50, General Design Criteria for Nuclear Power Plants, and Appendix A to 10 CFR 100, Seismic and Geologic Siting Criteria for Nuclear Power Plants, require that nuclear power plant structures, Revision 1 3.2-3 11/77

t MIDLAND 1&2-FSAR TABLE 3.2-1 DESIGN CRITERIA

SUMMARY

("

Design

~

FSAR Quality Code /

Seismic System / Component Section Location Group Standard Category SEISMIC CATEGORY I STRUCTURES Concrete 3.8.1 Containment Containment C

NA ACI-3188 I

l43 building AWS D1.1 C

NA ACI-318t28 I

Crane supports AISC AWS D1.1 C

NA ACI-318t23 I

Liner plate AISC

.~

AWS Dl.1 i

Penetration sleeve C

NA ACI-318i21 I

Personnel lock, C

NA ACI-318 t23 I

AISC 30 emergency airlock, ASME equipment hatch Containment 3.8.3 Internal Structures C

NA ACI-318tm I

f NSSS supports AISC AWS D1.1 Other internal C

NA ACI-318t2 I

AISC structures AWS D1.1 Auxiliary, 3.8.4 A

NA ACI-31882)

I AISC Building AWS D1.1 Diesel Generator 3.8.4 G

NA ACI-318'2' I

AISC Building AWS Dl.1 (sheet 1)

Revision 43 4/82 t

. s

,,,-,_--.--_,--,,,.-s.

l MIDLAND 1&2-FSAR TABLE 3.2-1 (continued)

Design:

FSAR Quality Code / -

Seismic

-System / Component Section Location Group Standard Category Engine driven G

D DEMA I

30 jacket water Pump Piping and valves 15 Engine mounted

• G NA DEMA I

27 Non-engine mounted 0,G C

III-3 I

30 Diesel Generator 9.5.6 Starting System i

Air receivers G

C III-3 I

Compressors G

NA NA NA Air dryers G

NA NA NA l15 Piping and valves l

Air receiver to engine G

C III-3 I

Compressor to receiver G

D B31.1 NA 15 Engine mounted G

NA DEMA I

t l

Filters G

NA NA I

Diesel Generator 9.5.7 Lubrication System Lube oil cooler G

C III-3 I

Lube oil sump G

C III-3 I

30 tank Auxiliary lube G

C III-3 I

oil pump Engine driven lube G

D DEMA I

oil pump Lube oil keepwarm C

C III-3 I

l30 l

pump l

Piping and valves Engine mounted C

NA DEMA I

l15 Aux skid mounted G

C III-3 I

1 I

Diesel Generator 9.5.8 l

Combustion Air j

intake and Exhaust System j

Turbocharger G

NA DEMA I

Intake air louvers G

NA NA I

(sheet 35)

Revision 34 6/81 L

e MIDLAND 1&2-FSAR TABLE 3.2-1 (continued)

Design 3

FSAR Quality Code /

Seismic System / Component Section Location Group Standard Category Intake filters G

NA NA I

l15 Ducts and dampers G

NA SMACNA I

Intake and G

NA NA I

exhaust silencers chemical Waste 9.5.9 System Motors E,T NA NEMA MG-1 NA Pumps E.T D

HI NA Piping and valves U,E,T D

B31.1 NA oily waste 9.5.10 System Motors E,P,T NA NEMA MG-1 NA Pumps E,P,T D

HI NA Piping and valves E,0,T,U,P D/NA B31.1 NA l21 Tanks P

D API-650 NA (sheet 36)

Revision 34

- g 6/81

• v f

MIDLAND 1&2-FSAR TABLE 3.2-1 (continued)

NOTES:

A. IEquipment hangers and supports are designed to the same quality classification as the associated equipment when the equipment is required for safety.

B. Bangers and supports of Seismic Category I systems in seismic Category I buildings meet the Seismic Category I requirements.

C. The trays and supports for safety-related cables meet Seirmic category I requirements.

Conduit and wirevays a,s well as the support materials for all raceways for safety-related cables O

are designed to maintain their integrity during a safe shutdown earthquake.

D. This equipment is seismically qualified as required to ensure that, during normal and safe shutdown earthquake conditions, fuel damage will not occur that would release radioactivity in excess of allowable limits.

"' Below are listed the definitions of abbreviations used in this table for each table heading.

FSAR Section Number:

Section where system, component, or structure is discussed.

NA:

The FSAR does not discuss this system, component, or structure.

Location A:

Auxiliary building C:

Containment E:

Evaporator and auxiliary boiler building l

G:

Diesel generator building B:

Guard house M:

Main chlorination facility 0:

Outdoors onsite (sheet 44)

Revision 30

. s 10/80 n,,

o f MIDLAND 1&2-FSAR TABLE 3.2-1 (continued)

P:

Oil waste treatment facility R:

Solid radwaste building S:

Office and service building T:

Turbine building U:

Underground onsite W:

Service water pump structure X:

Circulating water intake structure Y:

Makeup water pump structure Quality Group A, B, C, D:

Quality group cla'ssification as defined in Regulatory Guide 1.26.

NA Quality group classification as defined in Regulatory Guide 1.26 does not apply.

Design Code / Standard I:

ASME Boiler and Pressure Vessel Code,Section I III:

ASME Boiler and Pressure Vessel Code,Section III III-1, 2, 3:

ASME Boiler and Pressure Vessel Code, Section f

l III, Class 1, 2, 3 III-A:

ASME Boiler and Pressure Vessel Code,Section III, 39 Class A (1968)

IV:

ASME Boiler and Pressure Vessel Code,Section IV VIII:

ASME Boiler and Pressure Vessel Code,Section VIII ABMA:

American Boiler Manufacturers Association

~

ACI-318-63:

American Concrete Institute, " Building Code Requirements for Buildings" (for calculations initiated prior to February 1, 1973) j ACI-318-71:

American Concrete Institute, " Building Code Requirements for Building" (for calculations initiated on or after February 1, 1973) s, (sheet 45)

Revision 39 11/81

.:- --.- - --.-.. x.

y'

.9 MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) n.

IEEE-344:

InstituteofElectricalandElectronicEngineers)

Recommended Practices for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations IEEE-383:

Institute of Electrical and Electronic Engineers, Standard for Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations IEEE-387:

Institute of Electrical and Electronic Engineers, Trial-Use Criteria for Diesel-Generator Sets Applied as Standby Power Supplies for Nuclear Power Generating Stations IEEE-450:

Institute of Electrical and Electronic Engineers; Recommended Practice for Maintenance Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations IPCEA-5-19-81:

Insulated Power Cable Engineers Association; Rubber Insulated Wire an'd. Cable for the Transmission and Distribution of Electrical Energy MSAR-71-45:

Entrained Moisture Separator for Fine Particle Water-Air-Stream Service, Their Performance Development and 30 Status NA:

Design requirements specified by designer with appropriate consideration of the intended service and operation conditions

~

NEC:

National Electrical Code NEMA 1CS-1 to 110:

National Electrical Manufacturers' Association, Industrial Controls and Systems NEMA MG-1:

National Electrical Manufacturers' Association, Motors and Generators i

NEMA SM-22:

National Electrical Manufacturers' Association, Single Stage Steam Turbine for Mechanical Drive Service NFPA:

National Fire Protection Association SIP:

Standard Industrial Practice SMACNA:

Sheet Metal and Air Conditioning Contractors National Association, Inc.

(sheet 48)

Revision 44 6/82

, ~

~

9 i

,,n n,

,,,,,--w.--,.,-,

-,e-

,,w-.,-..-.-,--,

-,.,,,w,-.,,,,-

MIDLAND 1&2-FSAR S

TABLE 3.2-1 (continued)

TEMA-C:

Tubular Exchanger Manufacturers Association Class C TEMA-R:

Tubular Exchanger Manufacturers Association Class R UBC:

Uniform Building Code UL:

Underwriters' Laboratories Seismic Category I:

Construction in accordance with seismic requirements of Regulatory Guide 1.29 and Appendix A to 10 CFR 100 NA:

Not Seismic Category I t2'See referenced FSAR section for additional codes and standards applicable to these structures.

These components abd associated supporting structures must be 8:H designed to retain structural integrity during and after a Seismic Category I event but do not have to retain operability for protection of public safety.

The design basis requirement is prevention of structural collapse and damage to equipment and structures required for protection of the public safety.

For other applicable codes and standards see Section 71 and referenced FSAR sections.

Air handling unit fans and unit cooler fans are not rated in

'58 accordance with AMCA.

The entire unit is rated in accordance with ARI.

esiRefer to subsection 10.'2.1.3 for further discussion of turbine-generat'or codes and standards.

'" Refer to Table 3.2-6 j

""See Response to Regulatory Guide 1.143 in Appendix 3A.

I33

"'The engine-mounted fuel and cooling water lines are composed I'

of either ASTM A 53 or A 106, Grade A seamless steel pipe.

37 For pipe sections to be bent or formed, ASTM A 106 Grade B is used, with the compatible 106 Grade A pipe.

(sheet 49)

Revision 44 6/82 s,

?,"l...,, - -.,..,, -.

,_.,---.,,-.,,,,..,,,,------,,n,----n---

THIS RE?I. ACES LCST ORIGINAL

+

PROJECT Q-LIST ATTACHMENT "D" COVER SHEET CONSI:MERS POWER COMPANT I i]6 2 t a8.1.3.1 MIDLAND P& ANT UNITS 1 ANR 2 i

urDtANn, xiCarcaN JOB NO. 7 REV.NO.

10 Sheet i REV.

DATE REASON FOR CHANGE APPROVAL SIGNATURES DISCIPLINE TITLE b.

I I

l l

l l

b l

l t

. b l

L b

General Revision for the Purpose of Updating Informa on@MMMUTivil Struct/ Soils 5*M*03

,,sp

/4hj" Control Svste=s df 0. 6M1 Electrical 2

py' M,,mf/;jis%t); Mechanfeal/ Nuclear d

o mg. C CER Nuclear Insineer

~

%hdTM Project Engineer WTVSb M'?N!/c Consu=stNPcuerCo.

d M. N Are'hitett"-e T 4

-'7 W Civil St uet.!Som f

Updated the Civil section f/8/fa, to include underpinning q% 66 Control Svste s requirements W kl O Electrical sqhh

" Mechanical / Nuclear

",' Mg Nuclear Engineer t

.s

_ "MjM/s Project Engineer kMr% ; ___,

Consu=ers Power Co.

ED 15 REv.1 15 n

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M, SMEET ",[

SMEET SMEET SMEET

$ MEET SMEET SMEET y

i' 16 ELECTR: CAL hCH.(coht.) 'MICH (cont.)

j a :-,

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11 to 1

10 l 18 10 29 10 l l

1 10II 6 72 l 3 lo l 19 10 30 10 l y

2 10 3

10 20 10 l

31 10 l

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10 21 ID 32 10 l

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33 10 l l

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-4 10 1 22 10 23 10 l

ll CIVIL MECHM ICAL 24 10 l

1 10 1

10 25 10 l

l 2

10 2

10 26 10 l

l l

ll l

3 10 27 10 l

l H

3 10 4

10 4

10 28 10 l

ll 5

l 10 5

10

' CONTROL SYS.

ll ll 6

10 6

10 ll 1 10 l

ll ll l

i 7

10 7

10 2

10 N

l 8

10 8

10 3

10 l

ll ll ll 9

10 9

10 4

10 l

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10 l

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11 10 11 lo, l

l ll l

12 10 SERVIbES l

l l

l ARCHITkCTURE 13 10 l1 l 10 l

'l l

l ll l

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1 10 l 14 10 l

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l 15 10 l CPCO l

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DATE REVISIONS SY CHE*D APP *D NO.

DATE REvtSIONS l BY lCMCtl APP FACING SHEET JOB No. 7??O R E v.

MIDLAND PLANT UNITS 1 & 2

• g j

0 PROJECT Q-LIST Sheet 11 10 k

PROJECT Q-LIST lj$g33 CONSUMERS POWER COMPANY MIDLAND PLANT UNITS 1 AND 2 e Project Q-List is the master control document which' doentifies the structures, systems, components, and services that are important to safety and necessary to ensure 1) the

-integrity of the reactor coolant pressure boundary, 2) capability to-shut down the reactor and maintain it in a safe shutdown condition, or 3) capability to prevent or nitigate the consequences of accidents which could result in potential offsite exposure in excess of the guideline exposures of 10 CFR 100.

Q-listed portions of structures, systems, and components are designated as seismic Category 1 or Electrical Class lE.

lghi Application:

1.

Each item supplied by the Babcock & Wilcox Company is identified in the purchaser column by "B&W.*

Quality Assurance for the design, fabrication, shipment, and shop testing of such items is the responsibility of B&W and shall be in accordance with the latest revision of NPGD QA Manual 19AN.1 with exception for the CPCo contract.

2.

Items purchased by the Bechtel Power Corporation are jgg identified by "BPC.'

Quality Assurance for the design, procurement and installation of these ite=s is ths responsibility of Bechtel and shall be in accordance with the Bechtel NQAM.

3.

Items supplied by Consumers Power Company are identified in the purchaser column by 'CPCo."

Quality Assurance for the design, procurement, and installation of these items is the responsibility of CPCo and shall be in accordance with the CPCo QA Manual.

4.

All Q-listed items are subject to the requirements of the Consumers Power Company Quality Assurance Program for design, procurement, shipping, construction, preoperational testing, fuel leading, operation and l

maintenance.

Notes Referenced in the Q-List:

1.

All Q-valves, dampers, strainers, restricting orifices, lines, and pressure boundary'D, HVAC duct layout drawing 2bi instruments will be

~

identified on the system P&I system, isometric drawings and piping class summary l

sheets, and the applicable material requisition or specification.,

0020u

',7 Sheet 1, Rev. 10 1

1

.. Preiset Q-Lirta GCqntinuad)

All Q electrical instruments, devices, and components can be identified through the use of logics, loops,

/$i Ii62Ia schemes, and appiteable material requisition or specification.

2.

Portions required for control room emergency venti 1&fion.

3.

See penetration schedule Drawings M-301 and M-302.

4.

Mat'erial requisition number is not available at this time.

5.

See penetration schedule Drawing C-334.

6.

B&W supplied equipment is identified by a Bechtel/CPCo jhi file number.

This number is not the MR number for that item.

7.

Only the NDE that applies to field welding of Q-listed i

structures and systems as required by applicable specifications is Q-listed.

8._

Seismic Category 1 applies only to those components necessary to insure structural integrity of the system

/hi during a seismic event.

No electrical portions are seismic Category 1.

l 9.'

Identified and purchased with driven equipment.

i

10. This item is included on the Q-List to provide additional controls to ensure a 90% data recovery between March 1, 1975 and February 28, 1977 as required by Regulatory Guide 1.73.

Operation of the meteorology program after February 28, 1977, is for information only and is not Q-listed.

Meteorological tower instrumentation and its operation does not meet the Q-List definition of a safety-related system.

11. Piping, valves, hangers, and supports for 2 inch and smaller piping are field routed.

Refer to FSK-M drawings.

12. For control valves and solenoid valves which are part of these systems, see the control systems portion of Q-List.

13. This item covers Q-listed plans applicable to remedial jg soils activities.

The Q-List for this work is included in MPQP-2, Quality Plan for Remedial Soils Activities

- and soils-Related Work in Q Areas.

This quality plan is applicable for all aspects of the remedial soils activities and, as such, the activities and materials associated with this work are deemed Q-listed.

Q-listing provided in MPQP-2 covers activities, items, and structures beyond the requirements provided in the t

~

0020u Sheet 2, Rev. 10

---e----*--w

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wee-, - -

e.

v---w---ww-w www

-*w

1i8953 Pro eet Q-List (Continued)

FSAR.

This extension to provide quality assurance I.O2 D

program coverage over and above strictly safety-related I

I items will provide additional assurance that no activ.ity will adversely affect safety-related structures.

14. See Instrument Installation Summary J-705(Q) for guide to details of individual instrument installations.

See individual installation details for specific use of

/$i instrument valves, valve manifolds, instrument tubing and fittings, flexible metal hose, and instrument and tubing supports.

15. This item is CPCo purchaser responsibility and is identified by a Bechtel file number.

This number is not the MR number for that item.

16. This specification is Q listed for receipt, inspection, and placement only.

Design is not Q listed (based on ASLB order of April 30, 1982).

Supportine Documents 1.,

Mechanical reuipment List - An alphanumeric listing of equipment by equipment number with additional information such as MR number, equipment rating, location, vendor, P&ID number, and cost code.

Prepared and updated by the mechanical group.

Assigned Drawing 7220-M-485(Q).

M-485 is not definitive in designating Q or non-Q.

2.

Drawing Control Lee - A numerical listing of all

/b\\

drawings subdivided by~ discipline groups.

Centains the title, Q-designation, revision number, and revision date.

Prepared and updated by the project administrator on a monthly basis.

3.

Material Recuisition and specification Centrol Lee - A numerical listing of specifications and =sterial requisitions subdivided by discipline groups.

Contains such supplementary information as revision dates and purpose, date purchase order issued, and the supplier.

Prepared and updated by the Project Administrator on a monthly basis.

4.

Piping Class Summary Sheets - Specify the design and key operating conditions for each piping system and subsystem shown on the Piping and Instrument Diagram, 1

- and Piping Design Specifications.

A numerical listin's of piping by line number subdivided by piping class.

Contains such information as seismic class, design rating, service conditions, insulation class, and critical hanger designation.

Prepared and updated by the mechanical group.

Assigned Drawing 7220-M-480(Q).

0020u Sheet 3, Rev. 10

... ~..........r..........

~ ~ '

IiSS53

,' Proinct Q-List (Ccntinucd) 5.

Instrument Index - An alphanumeric' listing of Ii6275 1a*tru=*nt* *ad valve

• bY ia*trum*at numb *r with additional information such as MR number, location, and related drawings.

Prepared and updated by the Control Systems Group.

Assigned Drawing 7220-J-700.

Instrument Q categories of Og (functional) and Qo (pressure boundary only) are shown in the Q coltmn of the instrument index.

(The instrument index is not a "Q*

document because it is referenced for information only.)

6.

7220-G-33(Q) - Provides for Ehe purchase of Q-listed bulk materials / shelf items and special service orders, excluding ASME section III materials in accordance with the quality assurance requirements of specification 7220-G-33(Q).

Items procured under G-33 are not listed herein.

7.

Loeic and Loep Diaorams - Logic diagrams represent the functional logic of the equipment and clarify the intended use (Q and non-Q) of individual system components.

Loop diagrams represent the wiring of the system components (generally for analog systems) and indicate Q or non-Q usage of components.

8.

Insteument Installation Summary (J-705(Q)] - Provides Q status for all Bechtel-installed instrumentation.

Provides reference to applicable location drawing installation detail and instrument supports.

e I

's s

l 0020u Sheet 4, Rev. 10 l

l l

PROJECT Q-LIST Cn t-J MIDLAND UNITS 1 AND 2

-- g J0e NO. 1220 MECHANICAL PAGE 10 Identity Eclu tpoent Material Revision

_ Number Item / Description Purchaser Number Dratelnq pequisition 3

le 4.482 Piping EPC (1)

M-644(G)

M-104A(Q)

(only containment Penetration)

(11)

M-215fGI M-305(Q)

ISpec M-2eelg))

(Spec M-214tull m

10 4.483 valves arc (1)

M-640(Q)

M-125C(Ct W

(only Containment Penetration)

(11)

M-129A(0)

W M-204l0)

La3 le 4.484 Reactor aldq Penetration BPC (3)

M-301(UI, M-111(Q)

/

Plued Meads M-302(Q) 7 4.49 PLANT WATER STORACE AND M-449(O)

TRAt1SFER SYSTtH 10 4.491 Supports and Hangera BPC (1)

N-649(Q)

M-106(Q) tonly Containment Penetration)

(11)

(Spec M-326(Q))

(Spec M-343(oll (Spec M-36680),

M-217(Ql) le 4.492 Piping BPC (Il M-64910)

M-104A(Q) lonly containment Penetratloa)

(11)

M-215tgl M-305tol M-20410)

M-214(0) 10 4.493 valves (12)

BPC (1)

M-649(Q)

M-204(Ql, lonly Containment Penetrationi (111 M-125ClGI, M-12946blgl, M-3790(ui 10 4.494 seactor Bldg Penetration BPC (3)

M-301to),

M-111(Q)

Flued Heads l

M-3021QI 30 4.52 DIESEL ENGIlit, CEllERATOR, AllD INiSSORIES 10 4.521

• Diesel Engine, cenerator, and ePC ICl1 M/A M-18(Q)

Engine Mounted Aust!!arles 2cil to 4.522 Diesel Engine, cenerator, and BPC 1Gl2 M/A M-IS(0)

{

ingine Mounted Auaillarles 2Cl2 10 4.523 Supports & Hangere BPC (11 H-652(Q)

M-106(0),M-18(0) ispec H-326tGil (Spec M-3431ull (Spec M-366(Ql, M-217(ull

PROJECT 0-LIST

~*

t MIDLAND UNITS 1 AND 2 m

Joe No. 7220 i

MECHANICAL PAGE 19 identity Equipment Material US Devleton Mumber Item / Description Purchaser

_ Number Drawing pequisttlen to 4.524 toergency Diesel ott Tranater Pumpe aPC IP78A,e M-45210)

M-1910) 5.

and Motors 2P7en,s m

18 4.525 Piping SPC (1)

M-652(0)

M-194Al0),N-18(0)

M-452(0)

M-215(01 ut (11)

M-30510) c,3 M-10 (spec M-204(0))

(V.P.)

(Spec M-214(01) le 4.526 Emergency Diesel.oll Day SPC 1177A,a M-452(0)

M-64(0)

Tanks 2T77A,B 10 4.527 Emergency plesel ett storage Tanke BPC 17784,5 M-452(0)

M-64(0) 2T78A B 10 4.52s Valves arc (1)

M-652(0)

M-127A,B,6C(Cle I

(11)

M-1910) M-379910) l le 4.529 Jacket Watar Coolere BPC IE25A,5 M-419(0)

M-18(0) 1 2E25A,3 10 4.5210 Valves, Strainers, P11 tera and BPC M-452(0)

M-127e(0)

Miscellaneous Componente M-1810)

M-33610) 10 4.5211 Austilary Puel oil sooeter Puppe BPC IP-137A,3 M-18-26 M-18(0) 2P-137A,a (V.P.)

10 4.5212 Air Receivers BPC IT-934,8,C,D M-452(0)

M-1810) 2T-93A,B C.D 10 4.5213 Jacket Mater Standpipe BPC 17-94A,8 M-452(0)

M-18(O)27-94A,8 to 4.5214 Lube oil sump Tank BPC IT-61A,3 M-10-23 M-10(0) 2T-61A,3 (V.P.)

le 4.5215 Aust11ery Lube oit Pumps SPC IP-137A,5 M-10-23 M-10(0) 2P-137A,8 (V.P.)

.e 10 4.5216 Lube ott Coolere BPC IE-81A,e M-18-23 M-le(C) 2E-81A,8 (V.P.)

10 4.5217 Control Panetr and Instrumentation BPC IC111,112 M-15 (V.P.)

M-IS(0) 20111,112 1C231,232 2C231,232 10 4.5218 Intake Air Pltter BPC IP-19A,8,C,D M-18 (V.P.)

M-1810) 2F-19A,B,C,D e-

O PpoJECT 0-LIST e

a MIDt.AMD UNITS 1 AHO 2 JOB NO. 7220 MECMAMICAL PAGS 29 Identity Equi p nt Material Revision Musber Item /Deserlptton Purchaser Mumber Brawing pequisit loa le 4.5219 Intake Air Silencer BPC IM-100A,8,C,9 W-18 (V.P.)

M-ISIO) 2M-100A,B,C,D le 4.5228 Enhaust Silencer BPC 3M-101A,B M-18 (V.P.)

M-1980) 2M-100A,8 le 4.5221 Espansion Jointe BPC 1XJ-5201A,B, M-18 (V.P.)

M-13(g) 03 CD ru 2x.?-5201A,s, M

w C,D US w

lxJ-5202A,3, w

I

,/

C,D i

2xJ-5202A,B, C,0 6

4.53 REACTOR BUILDTHC NV & AC SYSTEN 1

DHl? I 7

4.531

---DELETED---

i i

Subcontract le 4.532 sectrculating Air Cooling BPC (1)

M-453(0)

M-15110)

Unit Ductwork and Supports M-515, (Including Installation)

Sh 110) 10 4.533 sydrogen Recombiners BPC 1VE54A,5 M-453(0)

M-169(0) l:

10 4.534 peactor sutiding socire. Air BPC IVM56A,5 M-45380)

M-163(0) l Cooling Unite C,D l

10 4.535 Reactor Building sectrc. Air BPC IVV57A,8 M-453(0)

M-16310) 1 Cooling Unit Fans C,D 10 4.536 seactor sullding Purge Penetra-BPC (1)

M-45310)

M-16850)

Lion Isolation valves (Includes M-513, M-127(0) 1 My Vent and Air Room Isolation Sh 180)

M-12980)

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Valves)

M-51410),

l-M-518,

)

Sh 110) 10 4.537

• Reactor sullding Penetration SPC (3)

M-30ll0)

M-111(0)

Flued Meads 10 4.530 Reactor Cavity Vent & Access Pipe BPC (1)

M-453f0)

M-104Al0) and Supports M-51710),

N-5l8,

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Sh 1(0) 0136u

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ATTACHMENT "E"

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PROJECT Q-LIST

s FOR DIE CONSUMERS POWER COMPANY 3

.-II MIDIAND PIANT UNITS 1 AND 2

-3i MIDIAND, MICHIGAN i{

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'E DISCIPLINE TITLE REV.

DATE REASON FOR CHANGE APPROVAL S1GN ATURES

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General Revision for the purpose

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of updating information and sto' rage W Civil "g/70 E

on ATS gy J'gontrol Syste:ns,

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of updating information and ggf/A Civil J

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Control Systems y ".

Qggpdu Electrical j$

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Kechanical l

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@//h a f Nuclear Engineer 7

g'c red:M Project Engineer Consuners Peser Co.

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J l'ROJECT Q-LIST MIDLAND UNITS 1 AND 2 PAGE 16 MEClIANICAL Joe NO. 7220 E00IP.

DWG.

M.R.

I REV.

IDENTI7T PUROIASER NO.

NO.

NO.

I No.

,No.

ITEM / DESCRIPTION l

~

BAPC (3)

M-301(Q) U 302(g)

M-111(Q) seactor 81dq Penetration 7

4.484 Flued Heads M-449(Q)

Pther WATER 570 RACE AND

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4.49 TRANSFER SYSTEM BAPC/BPC (1)

H-649(9)

M-106(Q) 7 4.491 Supports and Hangers (Spec M-326(Q))

(Spec M-343(Q))

1

)

BAPC/BPC (I)

M-649(Q) b104A(Q)

+ M-215(Q) 7 4.492 Piping M-305(Q)

>204(Q)

M-214(Q) s BAPC/BPC (1) b649(Q) b 204(9)

C W129A&B(Q) 7 4.493 Valves BAPC (3)

M-301(Q),N-302(Q)

M-111(Q) 7 4.494 Reactor Bldg renetration Flued Meaos M-452(Q)

~

8 4.52 EMERCENCY DIESEL CENERATOR AND 1

ASSOCI ATED SYSTf*MS BAPC IC11 N/A M-18(Q) 7 4.521 Diesel Cenerator 2G11 BAPC 1C12 N/A M-18(Q) 7 4.522 Diesel Cenerator 2G12 BAPC/

(1)

H-652(Q)

M-106(Q) i (Spec M-324(9))

7 4.523 Supports & Hangers BPC (Spec M-343(Q))

a BAPC 1P78A,B N/A 5 19(g) 7 4.524 Emergency Diesel 011 Transfer Pumps 2P78A.B and Motors BAPC/BPC (1)

M-652(Q)

U104A(Q)

M-21S(Q) l 7

4.525 Piping M-305(Q)

(Sgwe M-204(Q))

i (Tpec M-214(Q))

B4PC IT77A.B N/A M-64(Q)

I 7

4.526 Emergency Diesel Oil Supply 2TTI A.Il

7. ink r.

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PROJECT Q-I,lST

~

MIDI.AWD UNITS 1 ANf3 7 m

PACE 17 MErtlANICAL JOB 100. 7220 i

EQUIP.

DWU.

M.R.

I REV.

IDENTITT PtfRCHASER NO.

No.

38 0.

No.

38 0.

ITEM / DESCRIPTION 7

4.527 Emergency Diesel Oil Storage Tanks BAPC 1778A.B N/A M-64(Q) 2T70A.B BAPC/

(1)

M-652tq)

M-127B(Q)

'7 4.528 Valves BAPC IE25A.B N/A M-18(Q) e 4.529 Disel Generator Cooler 2E254.5 (Spec M-204(Q))

BPC

/

M-453(Q) 6 4.53 REACTOR BUILDING HV & AC SYSTEM UNIT 1 7

4.531

---DELETED---

Subcontract 8

4.532 Reactor Building Ductwork and BAPC/BPC (1)

M-453(9)

M-151(9)

Supports BAPC IVE54A,B M-453(Q)

M-149(Q) 7 4.533 Mydrogen Recombiners 7

4.534 Reactor Building Recire. Air BAPC IVM56A,8 M-453(Q)

M-163(Q)

C,D Cooling Units Reactor Building Recirc. Air BAPC IVV57A.B M-453(Q)

M-163(9) l 7

4.535 C,D Cooling Unit Fans

)

7 4.536 Reactor Building Purge Penetra-BAPC (1)

M-453(Q)

M-168(Q) tion Isolation valves (Includes H Vent and Air Room Isolation i

l Valves) 7 4.537 Reactor Building Penetration BAPC (3)

M-301(Q)

M-111(Q)

Flued Heads Reactor Cavity Vent & Access Pipe BAPC (1)

M-453(Q)

M-104A(9) 1 7

4.538 and Supports BAPC (1)

M-453(Q)

M-104A(Q)

Vent System Piping & Supports M-215(Q)

H, thin Reactor Ilustdang (Spec M-204(Q))

f 7

4.539 Wi l

(spec M-214(Q))

I I

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e,..'.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of:

)

Docket Nos. 50-329 OM

)

50-330 OM CONSUMERS POWER COMPANY

)

Docket Nos. 50-329 OL (Midland Plant, Units 1 & 2)

)

50-330 OL CERTIFICATE OF SERVICE I, Rebecca J. Lauer, hereby certify that copies of the letter to the Administrative Judges, dated August 12, 1983, in the above-captioned proceeding have been served upon all persons shown in the attached service list by deposit in the United States mail, first-class postage prepaid, this 12th day of August, 1982.

~

Rebecca Jf Lauer Isham, Lincoln & Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 (312) 558-7500 l

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a.,-

d ', ', es SERVICE LIST Frank J. Kelley, Esq.

Steve Gadler Attorney General of the 2120 Carter Avenue Stete of Michigan St. Paul, Minnesota.55108 Carole Steinberg, Esq.

Assistant Attorney General

, Environmental Protection Div.

Atomic Safety & Licensing 720 Law Building Appeal Board Lansing, Michigan 48913 U.S. Nuclear Regulatory Comm.

Washington, DC 20555 Cherry & Flynn Suite 3700 Mr. Scott W. Stucky Three First National Plaza Chief, Docketing & Services Chicago, Illinois 60602 U.S. Nuclear Regulatory Comm.

Office of the Secretary Washington, DC 20555 Mr. Wendell H. Marshall 4625 S. Saginaw Road Midland, Michigan 48640 Ms. Mary Sinclair 5711 Summerset Street Midland, Michigan 48640 Charles Bechoefer, Esq.

Atomic Safety & Licensing Board Panel William D. Paton, Esq.

U.S. Nuclear Regulatory Comm.

Counsel for the NRC Staff Washington, DC 20555 U.S. Nuclear Regulatory Co=.

Washington, DC 20555 Dr. Frederick P. Cowan 6152 N. Verde Trail Atomic Safety & Licensing Apt. B-125 Board Panel Boca Raton, Florida 33433 U.S. Nuclear Regulatory Co=.

Washington, DC 20555 James E. Brunner, Esq.

Consumers Power Company Jerry Harbour 212 West Michigan Avenue Atomic Safety & Licensing Jackson, Michigan 49201 Board Panel U.S. Nuclear Regulatory Comm.

Washington, DC 20555 Mr. D. F. Judd Babcock & Wilcox P.O. Box 1260 Ms. Lynne Bernabei Lynchburg, Virginia 24505 Mr. Thomas Devine Mr. Louis Clark l

Government Accountability Barbara Stamiris Project of the Institute l

5795 North River Road for Policy Studies l

Route 3 1901 Q Street, N.W.

l Freeland, Michigan 48623 Washington, DC 20009 l

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