ML20105C839

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Lists Questions Indicating Need for Increased Insp Effort Re Installation of Electrical Equipment,Wire Ways & Cable at Facilities
ML20105C839
Person / Time
Site: Midland
Issue date: 02/13/1981
From: Cook R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Knop R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20105C399 List:
References
FOIA-84-96 NUDOCS 8502090532
Download: ML20105C839 (2)
v • d • e


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  1. #40 UNITED STATES

[*g NUCLEAR ' REGULATORY COMMISSION 6

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cLEn Ettvn. stunois sour February 13,1981 u,.

1 NEMORANDUM FOR:

R. C. Knop, Section Chief FROM:

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

SUBJECT:

NEED FOR INCREASED INSPECTION EFFORT, ELECTRICAL AREA During the past week, I have received information which may indicate a need for a' rigorous NRC Inspection into the installation of electrical equipment, wire ways and cable at the Midland Site.

Some of the areas which appear to be in question are:

1) Separation criteria, as defined in the FSAR and IEEE Standards being violated. Construction Specifications are being considered " guides" in selected areas.
2) Zine based paint being applied to conduit joints and hangers located in the containment which is not approved for use in the containment and/or no inventory of the amount of " unauthorized" paint being used.

3)

Drilling into safety related walls for " temporary electrical attach-ments" (Q or Non-Q) without engineering approval to drill.

4) Void stamps being capriciously applied to electrical Deviation Reports in what appears to be an expediant way of dispositioning the Deviation Report.
5) New hire electrical QC personnel not being qualified and/or experi-enced and performing QC functions.
6) Audit findings pertaining to inplace storage of instruments being diluted and not being given strong management corrective action.

The above listed symptoms are considered indicative of additional ques-tionable practices pertaining to the installation of electrical equipments.

Therefore, an extensive rigorous inspection of electrical installation 8502090532 840517 PDR FOIA RICE 84-96 PDR

R. C. Knop, Section Chief 2

2/13/81

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appears eppropriate - particularly when considering that electrical con-struction activity is increasing at Midland.

Please advise.

r R. J. Cook Senior Resident Inspector Midland Site

Consumers power C0mpBRY Vice President - hojects, Engsneersng end Construction i

General offices: 1945 West Parnell Road, Jackson, MI 49201 * (517) 788-0453 February 13, 1981 Mr J G Keppler, Regional Director Office of Inspection and Enforcement US Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND PROJECT - DOCKET NOS 50-329, 50-330 ASSIGNMENT OF NRC CONTROL NUMBERS TO 50 55(e) REPORTS FILE: 0.h.9 UFI: 73*10*01 SERIAL: 11192

Reference:

(1) J G Keppler letter to J W Cock, dated January 22, 1981 In response to your request (Reference 1), we have given NRC Assigned Numbers to all Consumers Pcver 50 55(e) reports, beginning with our very first report made in 1973 to our most recent report made January 22, 1981.

A listing of all our 50.55(e) reports and their corresponding numbers is provided in Attachment 1 to this letter. We vill begin showing these NRC Assigned Numbers in the upper right hand corner of all future 50.55(e) correspondence.

&M (de WRB/1r CC:

Director, Office of Inspection & Enforcement US Nuclear Regulatory Co==ission Att Mr Victor Stello (15)

Director, Office of Management Information & Program Control, USNRC (1)

RJCook, USNRC Resident Inspector Midland Nuclear Plant (1)

2 Serial 11192 CC: CBechhoefer, ASLB Panel s

CALinenberger, ASLB Panel i FPCowan, ASLB Panel AS&L !.ppeal Panel MMCherry, Esq MSinclair CRStepehns, USNRC WDPaton, Esq UJ'fRC FJKelly, Esq, Attorney General SHFreeman, Esq, ASat Attorney General GTTaylor, Esq, Asst Atterney General WHMarshall GJMerritt, Esq, TNK&J Great Lakes QA Managers b

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Serial 11192

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I IDI 50.55(e) ITms DATM NRC ASSIGN m F "~'

DESCRIPTION NO.

DATE CPCO CPCO CPC0 LETTHt NO.

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IF APP.

REPORTED REPORT FINAL CIDSE NRC IUR REPolff (Ur CIASEOUT T3-01 0 k.9.2 B&W veld Filler Certification 01/16/73 02/12/73 08/22/79 (2)

IE Report 79-15, Pg %

T3-02 O.k.9 3 Cadwelds 11/09/73 12/10/73 (2) HRC Ltr of 12/26/73 T3-03 0.4.9.h B&W Prototype Testing 12/28/73 03/01/Tb 01/0h/80 (2)

IE Report 79-25, Pg 5 Th-01 0.4.9 5 Containment Fire 11/21/74 01/21/75 (3) NRC Ltr of 02/06/75 Tb-02 0.4 9.6 Containment Rebar Spacing 12/05/Th 04/23/75 (3) NRC Ltr

.of 05/C7/T5 76-01 0.k'.9.7 Missing Rebar Ob/13/76 05/21/T6 76-02 0.b.9.8 B&W Surveillance Capsu)e 0b/13/76 05/2T/77 06/21/TT Holder NRC Ltr of 06/21/75 (b) 76-03 0.b.9 9 Component Cooling water 13 12/10/T6 05/27/T7 The order for Pump Casing this component was cancelled.

77-01 0.b.9.10 Liner Plate Bulge 16 02/28/TT 08/15/78 12/78 (1)

(1) Includes any modifications of installi' tion after design release.

(2) Letter of R H Engelhen (NRC) to J F Mit11aj (B&W) of April 2h, 1973 accepts the steam generators for service.

(3) Letter of J 0 Davis (NRC) to S H llowe'.1 acknowle.lges report and states "sht>uld we require additional 1 1 forma tion...,

we wil l contact you.

(b) Letter of R F lleislanan (NRC) to S H !!nwell "...t:iis closes our control No. F31289F3, pres lously H01289 '3.

5

.I Imo 50.55(e) ITEMS DATE l

NEIT DAM DAM DAM &

NBC ASSIGNED FILE DESCRIPTICK NO.

DAM CPCO N

CPCO N

NO*

CO.

IF APP.

REPORTED REPORT FINAL CILSE NRC DUE RIT' ORT OtPF CLOSEOLFF 77-02 0.k.9.11 Tendon Sheath IT 0k/19/T7 08/12/77 10/T8 (1)

IE Repo-t 79-15 Pg k T8-10 0.k.9.22 Qualtrication Test Review 25 11/13/78 03/27/81 78-11 0.k.9 23 Pressuriser Heater System 12/0T/78 ok/01/81 i

78-12 0.k.9.2k Penetrations. Termination 26 12/22/78 05/25/79 06/08/79 (1)

Defects 78-13 0.k.9 25 Control Room Air Filter Systa 27 12/27/78 03/09/T9 01/80 Inadequate Wiring-79-02 0.k.9.27 Feedvater System Pipe Spool -

29 05/22/T9 12/10/T9 Impact Properties 79-01 0.k.9.26 Main Control Status Display 28 05/29/79 07/20/T9 Panels (Soldered Connections) 79-07 0.k.9.32 Contairment Air Coolers, 30 07/09/79 10/15/79 Cooling Water, Supply Pressure 79-03 0.b.9.28 Small Break /RC Pump Operation NA 07/16/T9 05/30/81 Interaction 79-Ok 0.k.9.29 States Sliding Links, Defee-32 -

07/19/79 03/03/80 tive Clip Presents Cinching 79-05 o.h.9.30 Tendon Wire Length variation 33 07/27/T9 10/31/T9 02/16/80 Closed in I&E Report 60-01 Page 16/1T 77-03 0.k.9.12 ITT crinnell Pipe Supports NA 10/27/77 09/08/78 78-01

, 9.k.9 33 BCP Motor Flange NA 01/18/78 01/31/T9 1

Personnel Air locks 20 02/02/78 09/29/78 78-03 g0.k.9.15 i

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.f I40 50.55(ei ITEMS DATE NRC ASSIONED TILE DESCRIPTION NM M

DAM DAM &

NO.

DATE CPCO CPCO CPCO LETTER NO*

IF APP.

REPORTED REPORT FINAL CIASE NBC DUE REPORT OLFr Ctmeru_sy 78-02 0.4.9.1b DeceF Neat Reu m al Pumps NA 02/02/78 06/02/T8 08/78 12/28/78 NRC Report 78-15 78-Ok 0.%.9.16 RPS Loss of Ground NA 03/08/78 01/11/80 78-05 0.k.9.17 Spray Piping Supports 22 03/22/78 12/21/79 78-06 0.b.9 18 Small Break Analysis NA 04/12/78 03/12/T9 78 07 0.b.9.19 Seismic Cable Trey Supports.

23 Ok/lb/T8 09/08/T8 78-08 0.k.9.20 Diesel Generator Building 09/07/T8 02/07/80 Transferred to Foundation Licensing to follow.

78-09 0.4.9.21 Battery Racks NA 10/20/78 01/31/T9

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79-06 0.4.9.31 Station Batteries NA 08/01/79

'08/23/T9

,79-08 0.%.9.33 M11t1 Drop-in Anchors NA 08/31/79 12/21/T9 79-10 0.k.9 35 RV Anchor Bolt Failure 37 08/31/79 3/31/81 79-11 0.4.9.36 Boration Systen Inadequacies NA 10/02/T9 T/17/81 79 12 0.b.9 37 Unit 2 Shield Wall Coatings 35 11/13/79 3/1/81 80-01 0.k.9.38 Letdown Cooler Supports MA 02/26/80

-h/15/81 79-09 0.k.9.34 Oculd Part 21 NA 09/21/79 10/15/79 80-02 0.4.9.39 B&W/Bechtel Inconsistencies 38 05/02/80 10/31/80 on Cross-Referencing for B&W t

Supplied Items 80-03

'0.4.9.40 ECC Actuation System Cross-39 06/18/80 07/17/80 over

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I i*t IA0 50.55(e) ITses DATE

. DESCRIPT105 MCAR NEIT DATE DATE DATE &

l NBC ASSIGNED FILE l

30.

30.

NO.

.DATE CPCO CPCO CPCO LETTER j

IF APP.

REPORTED REf0RT FINAL CIDSR NRC

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I 80 04 0,b.9.41 NELBA Restraint Design 40 '

8/21/80 -

4/3/81 80-05 0.4.9.42 Swer Strut Rod Ehde Defielene) b2 9/24/80 2/27/81 l

80-06 0.4.9.h3 Component Cooling water Desis:

43 10/8/80 3/31/81

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%k 11/17/80 3/12/81 80-06 0.%.9.45 ECCAS Cabinets.

11/18/80 2/27/81 80-09 0.h.9.b6 Iow Alloy. Quenched &

45 11/26/80 3/31/81 t-Tempered Bolting T/8" Dia I

and Greater J

81-01 0.h.9.47 Limitorque Operator -

46 1/lb/81 2/13/81 Terminal Strip Voltage Rating i

81-02 6.4.9.48 seismic Model or Auxiliary 47 1/21/81 2/20/81 Building 81-03 0.%.9.%9 Bormted Water Storage Tank b8 1/22/81 2/21/81 Foundation k

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'd J O Selby Chasrvean of the Board and President

. General offices: 212 West Michigan Avenue, Jackson. MicNgan 49201 * ($17) 788-1600 bby 8, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 MIDLAND PROJECT PROJECTED LICENSING SCHEDULE FILE: 0505.2 UFI: 70*01 SERIAL: 12176

Dear Mr. Denton:

On January 16, 1981, I wrote a letter to John Ahearne, then Chairman of the NRC, expressing my concern with regard to NRC's projected licensing schedule for the Midland Plant as given in NRC's November 21, 1980 Status Report to Congress. Your response of February 10, 1981 stated that a reexamination of facilities such as Midland with construction completion dates beyond CY 1982 was in progress. In addition, you indicated that upon completion of the re-examination you would provide me with the results and a description of the effect on Midland 2.

Recently we received a copy of NRC's March 31, 1981 Status Report to Congress.

Table 2 of that report, while indicating an NRC decision date of 7/83, in agreement with our current Midland 2 fuel load date, retains the NRC's previously scheduled SER date of 7/82.

Thus, the post-SER licensing duration has been further shortened and this' duration of one year has been applied to all units scheduled for completion during CY 1983.

I continue to believe that the NRC's scheduled SER issue date for budland is unrealistic and places undue pressure on the post-SER licensing process.

In particular an ACRS (SER-SSER) duration of only one month is not reasonable for Midland. Likewise, experience in the past with heavily contested hearings on Midland indicates the need for a longer than average hearing duration.

As stated in my March 2,1981 response to your letter of February 10, 1981, I support the establishment of realistic schedules and proper prioritization for all plants. Thus, I am pleased to note in the March 31 Status Report that the Staff is attempting to reconcile the discrepancies between NRC and applicant construction completion dates.

In this regard, recent Midland construction progress is demonstrating the required installation rates to achieve our over-all construction schedule.

In fact, during the past five weeks ending April 26, the project installed 738,000 ft of wire and cable and also exceeded scheduled 00 /

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Mr. Harold R. Denton May 8, 1981 2

s quantities of other critical commodities such as conduit, small pipe and small pipe hangers. We are confident that there is a sufficient engineering backlog to sustain the required installation rates. We also believe, subject to Staff review, that our design is based on a realistic scope that properly incorporates the post-TMI issues. We feel that our current progress is indicative that our planned Unit 2 fuel load date of July 1983 is attainable.

I am also encouraged by an increased amount of licensing review activity by the Staff on the Midland docket, particularly the Staff participation in che Design Review Board meeting on Cold Shutdown and a subsequent Auxiliary Feedwater technical review meeting in late April.

The critical nature of the Midland licensing schedule dictates the need for additional similar meetings as well as other alternative review techniques, as appropriate; and I request your continued positive response to our initiatives in this regard.

Nevertheless, I believe that the Midland licensing schedule presented in Table 2 of NRC's March 31, 1981 Status Report to Congress represents an unacceptable risk to Consumers Power, its customers, and its stockholders in terms of the likelihood of our obtaining a license to load fuel in Unit 2 upon completion in July 1983. NRC Chairman Hendrie stated on P. 4 of that report that the Table 2 " schedules are based on completing the licensing process prior to the applicant's estimated construction completion date."

I request that you reassess the realism of the NRC's current licensing schedule for Midland and, specifically, that you consider advancing the schedule for issuance of the Midland SER by six months to January of 1982. My staff at Consumers Power is available to s'upport the NRC staff in any way you consider appropriate to attain this more realistic licensing schedule.

Yours very truly, J. D. Selby JDS:im O

e Date ROUTING AND TRANSMITTAL SUP g_y., gj 70: (Name, office symbol, room number, initials Date building, Agency / Post)

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The following is a " retype" of a letter from Barbara Stamitis to James G. Keppler, RIII. Retyping was necessary for Telefax transmission due to light copy.

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T May 26, 1981 i

Dear Mr. Keppler,

j I want to thank you again for meeting with me last Thursday in Midland. Your directness and openness encourage me to consnunicate l

with you once more.

I am including my recent motions which we briefly discussed, I am also including some 1980 audit reports as it is my understanding j

from Consumers and some NRC personnel that they may not have been presented to the NRC.

I also wish to have this final input into your upcoming QA decision. You considered Consumers QA acceptable in 1979 because they identify their own deficiencies. Although I consider such l

identification a basic obligation, even this is questionable in 1980 considering 1) their denial of a QA breakdown in soils in their Answer to Notice of Hearing, 2) their handling of the Zack matter, and

3) Bechtel's withholding of information related to the Pipe Whip l

Restraint problem (which dates back to I&E report 78-10).

i Even more important than the identification of problems, is the resolution of problems once identified.

It is apparant in almost i

every major problem area Consumers has encountered over the years, that the weeding out of problem sources, and ultimate resolution of the problems has not occurred in a timely manner, on their own initiative, as you are well aware.

Perhaps the best example of this is Consumers acceptance of poor quality performance by-Bechtel, which has been the underlying 1

cause of so many problems. Even when the problem has been identified, as in their 1975 lawsuit against Bechtel for negligence in construc-tion and design of Palisades, or as in their response to 50-54f q.23 as to root causes of the soil settlement problem, these Bechtel

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deficiencies are condoned and destined to repeat themselves.

Your Nov. 24, 1980 SALP report and the post SALP assessment i

of their QA reform certainly indicated need for improvement. And although I am not in a position to obtain hard information about this most recent period of QA performance, I understand that Mary l

Sinclair has a tape in which workers discuss their reluctance to report QA matters, which may confirm what has heretofore been only i

hearsay.

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Most recently, I read in today's paper that Consumers' disagrees with the NRC on the necessity of halting work on the maall bore pipes while audit reports on the problem are completed. Once again they seek to proceed at their own risk, without examining the. full extent

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o'r root cause of the problem. To me, this says more about Consumers 4

'Y managerial attitude concerning QA problems, and how it remains the same, than any statements of intent or impressive improvements as demonstrated in the inspection last week.

l I do not criticize the inspection itself as it too'k place last j

week. But I am terribly concerned with what I understand the NRC intends to do with that report in terms of ignoring five years of j

past QA deficiencies because of it.

At the Nov. 24, 1980 SALP meeting, you said that you intended to lay out the broad overview of Consumers QA performance as you did at that meeting, and let the Board decide "is their QA still defensible?" Do you now intend

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to present a conclusion instead?

I have no choice but to raise these questions and concerns, A

for I am deeply distressed with what I see developing and being j

finalized so quickly. My concern goes beyond the effect of this pending stipulation on my case or contentions, to its profound implications for basic health and safety questions, in the rest of the proceeding and for NRC regulation as a whole.

Sincerely, Barbara Stamiris i

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UNITED STATES NUCl. EAR REGULATORY COMM10SION o

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JUN 9 1981

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l'r. J. D. Selby, President f. Chief i

Er.ccutive Officer Ccncuncrs Power Ccorany P.121l cst I'lchican /.vonne i

Jackson, litchigan 49201

Dear l'r. Selby:

l I?o presently have under review cleost thirty applications for operating 4

licenses. For your application, as well as nost others, we are comitting resources to assure that staff revfcus are conpleted on a schedule ccnststent with your projected plant conplotfon date. Frclininary schedules for facilities projecting plant cocpletion in late 1982 or in 1983 were

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on April 30, 1981 in connection with the "Bevill Report."provided to Congress Your schedule was developed using your estinated construction completion date and a set of standard hearing assumptions.

The preliminary hearing schedules assume a standard eleven-nonth: time period from the issuance of the final Supplement to the Safety Evaluation Report 4

(SSER) to the tiRC decision date.

This tine perfod incorporates the efficiency j

reasures projected to be in place in the near future.

It is based on five

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r.onths from issuance of the SSER to the start of hearing, five months from i

start of hearing to the initial decision by the Atonic Safety Licensing

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floard, and one conth from tie initial decision to the Connission's decision j

date. These assumptichi, and your relative priority, will be re-examined on a case-by-case basis after the Comission corpletes its consideration of proposed changes to the regulations.

To essure proper internal resources allocation, it is important that you provide us a* realistic and up-to-date projected construction conpletion date.

Because of man to fall in a " window" power limitations each review will be scheduled of tfne wherein our reviews must be conpleted. An unexpected change of your completion date or your ability to provide needed infomation in accordance with this schedule will likely have an impact on the schedule for your review. Accordingly, you should examine your schedules in the attached Table and. confim or change your construction completion i

date within 14 days of recefpt of this letter.

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You should also provide quarterly updates thereafter until issuance of the Safety Evaluation Report for the facility.

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For the staff to c
cet these sclicdules, all information concerning your cpplication idcntified as nceded rust be provided by you or your contractors at least cight ucchs prier to the date scheduled for the issuance of the Safety Evaluation Ecport. Ycu ci:culd consic'er arrenc.ing to h6ve :cubers of your staff who can represent you and who can resolve any last ninute open itens, in residence near the I; llc offices in Cethesda for c tuo ucek period starting six uceks irvedtately preceding the scheduled date for issuing the Safety Evaluation Report. Ycur staff should contact the I.fcensing Project l'anager for specific needs related to the revicu of your appifcation.

Your cooperation is appreciated.

Sincerely, syd fWW r 3.Ee.iten Ifarold R. Denton, Director Office of !!uclear Reactor Rerulation ec: See next page e

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MIDLAND Mr. J. D. Selby, President & Chief Executive Officer Consumers Pouer Conpany

.'1945 !! cst Parnall Road

Jackson, Michigan 49201 cc
Michael I. Miller, Esq.

Mr. Don van Farrowe, Chief Ronald G. Zamarin, Esq.

Division of Radiological Health Alan S. Farnell, Esq.

Department of Public Health Isham, Lincoln & Beale P.O. Box 33035 Suite 4200 Lansing, Michigan 48909 1 First National Plaza

Chicago, Illinois 60603 William J. Scanlon, Esq.

2034 Pauline Boulevard James E. Brunner, Esq.

Ann Arbor, Michigan 48103 Consumers Power Company 212 West Michigan Avenue U.S. Nuclear Regulatory Commission Jackson, Michigan 49201 Resident Inspectors Office Route 7 Myron M. Cherry, Esq.

Midland, Michigan 48640 1 IBM Plaza Chicago, Illinois 60611 Ms. Barbara Stamiris 5795 N. River Ms. Mary Sinclair Freeland, Michigan 48623 5711 Summerset Drive Midland, Michigan 48640 Mr. J. W. Cook Vice President Frank J. Kelley, Esq.

Consumers Power Company Attorney General 212 West Michigan Avenue State of Michigan Environmental Jackson, Michigan 49201 Protection Division 720 Law Building..

Lansing, Michigan 48913 Mr. Wendell Marshall Route 10 Midland, Michigan 48640 Mr. Steve Gadler 2120 Carter Avenue St. Paul, Minnesota 55108 O

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-T

TABLE 2_

CY 1983 FLANTS DIVISIONOFLICENSING-4[.6/81' Estima'ted~

ASLB NRC Applicant s

Delay

. j' Issue Issue ACRS ISSUE Issue Start of Initial Occision Construction (Months)

DES SER MTG FES SSER Hearing (1)

Decision (1)

Date(1)

Completion Plant e Callawa'y1/2 0

09/81 50/81 11/81 01/82 11/81 04/82 09/82 10/32 10/82 St. Luc'te 2 0

09/81 1 0/81 11/81 01/82 11/81 04/82 09/82 10/82 10/82 Palo V$rde 1/2/3 0

1 0/81 11/81 12/81 02/82 12/81 05/82 10/82 11/32 11/82

    • Seabrook 1/2*

0 11/81 01 / 82 02/82 03/82 02/82 07/82 12/82 01/33 01/83 12/82 01/33 01/83 Cit nted 1 0

11/81 01 /8 2 02/82 03/82 02/82 07/82 Wolf Creek 1 0

01 /82 04/82 05/82 06/82 05/82 10/82 03/83 04/83 04/83 Byron 1/2 0

01 / 82 04/82 05/82 06/82 05/82 10/82

.03/83 04/83 C4/83 Perry 1/2 0

02/82 05/82 06/82 07/82 06/82 11/82 04/83 05/83 05/83 Midland 1/2 0

" 04/82 07/82 08/82 09/82 08/82 01/83 06/83 07/83 07/83

    • Catawba 1/2 0

05/82 08/82 09/82 10/82 09/82 02/83 07/83 08/83-08/83

06/82 09/82 10/82 11/82 10/82 03/83 08/33 09/83 09/83 River Send 1/2 0

07/82 10/82 11/82 12/82 11/82 04/83 09/83 10/83 10/83

],

NOTES:

FSAR not tendered Schedules subject to change upon resolution of NRC and applicant construction completion differences (1) 8ased on a standard eleven-month assumption' from issuance of SSER to NRC Decision Date k

O

~

i

Bechtel Associates Professional Corporation 777 East Eisenhower Parkway Ann Arbor, Michigan

+ 3,.

Med Address P O. Box 1000, Ann Arbor, Michgan 48106 1

June 29, 1981 To Whom It May Concern:

Enclosed you will find a revision to your set (s) of the Midland Plant Reference Drawings.

Please incorporate into your set (s) as appropriate, and if you have any questions, feel free to call L. Hultquist or D. Allred at (313)954-7861.

Thank you, 4

e i

e

MIDLAND PLAN

  • REFERENCE DRAWINGS INDEX

~

PLANT ARRANGEMENT Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

s

" A-62 7

Access Control - El. 632'-6" and 634'-6" 12.5-1 A-123 6

Fire Protection - Reactor and Auxiliary 9A-7 Building Plan at El. 614'-0" A-126 6

Fire Protection - Reactor and Auxiliary 9A-10 Building Plan at El. 659'-0" i

A-150 4

Minimum Radiation Shielding Requirements, 12.3-1 Reactor and Auxiliary Building, Plan of El. 568'-0" A-153 4

Minimum Radiation Shielding Requirements, 12.3-4 Reactor and Auxiliary Building, Plan of El. 634'-0" A-158 Sh 1 3

Minimum Radiation Shielding Requirements, 12.3-9 Reactor and Auxiliary Building, Plan of El.

634'-6",

648'-6",

and 659'-0" A-158 Sh 2 3

Minimum Radiation Shielding Requirements, 12.3-42 Solid Radwaste Building, Plan of El.

634'-0" and 652'-0" A-170 4

Radiation Zoning - Reactor and Auxiliary 12.3-16 Buildings Plan of El. 568'-O" A-171 3

Radiation Zoning - Reactor and Auxiliary 12.3-17 Buildings Plan of El. 584'-0" A-172 4

Radiation Zoning - Reactor and Auxiliary 12.3-18 Buildings Plan of El. 599'-0" A-173 7

Radiation Zoning - Reactor and Auxiliary 12.3-19 Buildings Plan of El. 614'-0" A-174 3

Radiation Zoning - Reactor and Auxiliary 12.3-20 Buildings Plan of El. 635'-6" A-175 4

Radiation Zoning - Reactor and Auxiliary 12.3-21 Buildings Plan of El. 645'-0" A-176 4

Radiation Zoning - Reactor and Auxiliary 12.3-22 Buildings Plan of El. 659'-0" A-177 2

Radiation Zoning - Reactor and Auxiliary 12.3-23 Buildings Plan of El. 674'-0" & 685'-0" 1

Revision 34 6/81

+

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

PLANT ARRANGEMENT Bechtel FSAR Dwq No.

Rev.

Title '

. Fig. No.

I A-178 Sh 1 4

Radiation Zoning - Solid Radwaste and 12.3-24 Auxiliary Buildings Plan of El. 634'-6" 648'-6" and 659'-0" A-178 Sh 2 5

Radiation Zoning - Solid Radwaste 12.3-43 i

Building Plan of El. 634'-0" and 652' "

A-179 1

Radiation Zoning - Turbine Building -

12.3-25 Unit 1 Plan of El. 614'-0" A-180 0

Radiation Zoning - Turbine Building -

12.3-26 Unit 1 Plan of El. 634'-6" l

A-181 0

Radiation Zoning - Turbine Building -

12.3-27 Unit 1 Plan of El. 659'-0" and 695'-5/16" A-182 0

Radiation Zoning - Turbine Building -

12.3-28 Unit 2 Plan of El. 614'-0" A-183 0

Radiation Zoning - Turbine Building -

12.3-29 Unit 2 Plan of El. 634'-6" A-184 0

Radiation Zoning - Turbine Building -

12.3-30 Unit 2 Plan of El. 659'-0" and 695'-5/16" C-3 6

Station Arrangement 1.2-1 J-299 Sh 1 8

Engineered Safety Features Actuation 7.3-2 System - RBIS-II, RBSAS, RBCAS, and RBIS-I J-299 sh 2 8

Engineered Safety Features Actuation 7.3-3 System - MSLIS J-299 Sh 3 8

Engineered Safety Features Actuation 7.3-4 System - AFWAS, RAS, Loss of Reactor Coolant Pump J-299 Sh 4 b

Engineered Safety Features Actuation 7.3-5 System - CRIS J-299 Sh 5 7

Engineered Safety Features Actuation 7.3-6 System - DG Start, LOP /ECCAS Sequence J-299 Sh 6 6

Engineered Safety Features Actuation 7.3-7 System - FPVAS 2

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continund)

PLANT ARRANGEMENT Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

-< J-299 Sh 8 6

Engineered Safety Features Actuation 7.3-8 i

System - ECCAS, Conditioning Cabinets J-299 Sh 9 4

Engineered Safety Features Actuation 7.3-9 System - Reverse Feedwater from Steam Generators A and B J-725 8

Control Room Equipment Arrangement 6.4-3 M-1 14 Equipment Location - Reactor and 1.2-2 Auxiliary Buildings - Plan at El. 568'-0" M-2 12 Equipment Location - Reactor and 1.2-3 Auxiliary Buildings - Plan at f

El. 584'-0" M-3 12 Equipment Location - Reactor and 1.2-4 Auxiliary Buildings - Plan at El. 599'-0" M-4 11 Equipment Location - Reactor and 1.2-5 Auxiliary Buildings - Plan at El. 614'-0" M-5 14 Equipment Location - Reactor and 1.2-6 Auxiliary Buildings - Plan at El. 634'-6" M-6 13 Equipment Location - Reactor and 1.2-7 Auxiliary Buildings - Plan at' El. 645'-0" M-7 Sh 1 11 Equipment Ldcation - Reactor and 1.2-8 Auxiliary Buildings - Plan at El. 659'-O" M-7 Sh 2 12 Equipment Location - Reactor and 1.2-9 Auxiliary Buildings - Plan at El. 674'-0" and 685'-0" M-8 7

Equipment Location - Auxiliary Building 1.2-10 Seption A-A M-9 8

Equipment Location - Reactor and 1.2-11 Auxiliary Buildings - Section B-B 3

Revision 34 6/81-

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continusd)

\\

PLANT ARRANGEMENT i

Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

u,.

I M-10 7

Equipment Location - Reactor Building 1.2-12 Sections C-C and D-D M-11 Sh 1 6

Equipment Location - Auxiliary Building 1.2-13 Section E-E M-11 Sh 2 6

Equipment Location - Auxiliary Building 1.2-14 Section F-F M-12 Sh 1 9

Equipment Location - Auxiliary Building 1.2-15 Solid Radwaste and Railroad Bay 11.4-4 M-12 Sh 2 4

Equipment Location - Solid Radwaste 1.2-16 Building 11.4-5 M-13 0

Equipment Location - Auxiliary Building Roof Plan of El. 707'-0" M-14 10 Equipment Location - Turbine Building --

1.2-17 Unit 1 - Plan at El. 614'-0" M-15 7

Equipment Location - Turbine Building -

1.2-18 Unit 1 - Plan at El. 634'-6" M-16 5

Equipment Location - Turbine Building -

1.2-19 Unit 1 - Plan at El. 659'-O" and 695'-5/16" M-17 14 Equipment Location - Turbine Building -

1.2-20 Unit 2 - Plan at El.

614'-0".

M-18 11 Equipment Location - Turbine Building -

1.2-21 Unit 2 - Plan at El. 634'-6" M-19 11 Equipment Location - Turbine Building -

1.2-22 Unit 2 - Plan at El. 659'-0" and 695'-5/16" M-20 4

Equipment Location - Turbine Building -

1.2-23 Unit 2 - Sections A-A, B-B and C-C M-21 2

Equipment Location - Service Water Pump 1.2-24 Structure Plans and Sections M-22 Sh 1 7

Equipment Location Plan - Evaporator 1.2-28 Building Ground Floor El. 634'-6" 4

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

PLANT ARRANGEMENT Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

M-22'Sh 2' 3

Equipment Location Plan - Evaporator 1.2-29 Si Building Operating Floor El. 653'-6" M-22 Sh 3 2

Equipment Location - Evaporator 1.2-30 Building Plan at El. 662'-6" and Above and Section E-E - Later M-23 4

Equipment Location - Evaporator Building 1.2-31 Sections A-A, B-B, C-C, D-D, and F-F -

Later M-24 Sh 1 3

Equipment Location - Cooling Pond Makeup 1.2-25 Water Pump Structure Plan and Section M-24.Sh 2 3

Equipment Location - Cooling Pond Makeup 1.2-26 Water Intake Structure Plan and Sections M-25 Sh 1 3

Circulation, Water, Storage, Chlorina-1.2-32 tion and Cooling, Building, Plan at El. 634'-6" M-25 Sh 2 2

Circulation, Water, Storage - Chlorina-1.2-33 tion and Cooling, Building Plan at El. 600'-0" M-26 4

Equipment Location - Diesel Generator 1,2-27 Building Plan and Sections Diesel Generator Building 3.8-55 ELECTRICAL Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

E-001 5

Plant Single Line Diagram 8.3-1 E-002 Single Line Meter and Relay Diagrams - Later.

E-003 4

Generator and Station Power Sources Unit 1 E-004 4

Geherator and Station Power Sources Unit 2 i

E-005 8

6,900 and 4,160 Volt Systems, Unit 1 i

j 5

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

ELECTRICAL Bechtel FSAR Dwg No.

Rev.

Title '

Fig. No.

I E-006 8

6,900 and 4,160 Volt Systems, Unit 2 E-009 5

Rebciler and Cooling Towers 4,160 Volt System E-011 5

Class 1E 480 Volt Load Centers, Unit 1 E-012 5

480 Volt Load Centers, Unit 1 E-014 5

480 Volt Load Centers, Common Loads E-015 5

Class 1E 480 Volt Load Centers, Unit 2 E-016 5

480 Volt Load Centers, Unit 2 E-021 7

250 and 125Vdc Systems, Unit 1 8.3-39 E-022 7

250 and 125Vdc Systems, Unit 2 8.3-40 E-023-1 7

120Vac Instrument and Preferred 8.3-2 Systems, Unit 1 Sh 1 E-023-2 3

120Vac Instrument and Preferred 8.3-2 Systems, Unit 1 Sh 2 E-024-1 7

120Vac Instrument and Preferred 8.3-3 l

Systems, Unit 2 I

E-025 Sh 1 2

Synchronizing Diagram E-025 Sh 2 2

Synchronizing Diagram E-026 Sh 1 1

Phasing Diagram Unit 1 E-026 Sh 2 1

Phasing Diagram Unit 2 E-051 6

Generators and Main Transformers-Later E-052 6

6,900 Volt, and 4,160 Volt, Systems-Later E-053 6

4,160 Volt Class 1E System-Later E-054 2

Startup and Station Power Transformers E-058 5

Class 1E 125Vdc System E-059 Sh 1 4 Two Line Meter and Relay Diagram, 125/250Vdc System 6

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continu3d)

ELECTRICAL Bechtel FSAR Dwg No.

Rev.

Title

. Fig. No.

s "iE-059 ~ Sh 2 0 Two Line Meter and Relay Diagram, 125/250Vdc System P& ids Bechtel FSAR Dwq No.

Rev.

Title Fig. No.

M-400 Sh 1 3

Piping and Instrumentation Diagram 1.1-1 Legend M-400 Sh 2 4

Piping and Instrumentation Diagram 1.1-2 Legend M-400 Sh 3 4

Piping and Instrumentation Diagram 1.1-3 Legend M-401A 3

Reactor Coolant and Pressure Control -

5.1-1 Unit 1 Sh 1 M-401B 3

Reactor Coolant and Pressure Control -

5.1-1 Unit 1 Sh 2 M-402A 3

Reactor Coolant and Pressure Control -

5.1-2 Unit 2 Sh 1 M-402B 3

Reactor Coolant and Pressure Control -

5.1-2 Unit 2 Sh 2 M-403 Sh 1A 4 Makeup and Purification Unit 1 9.3-31 Sh 1 M-403 Sh 1B 3 Makeup and P'urification Unit 1 9.3-31 Sh 2 M-403 Sh 2A 3 Makeup and Purification Unit 1 9.3-32 Sh 1 M-403 Sh 2B 3 Makeup and Purification Unit 1 9.3-32 Sh 2 M-404 Sh 1A 4 Makeup and Purification Unit 2 9.3-33 Sh 1 M-404 Sh IB 3 Makeup and Purification Unit 2 9.3-33 Sh 2 7

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR Fig. No.

Dwg No.

Rev.

Title s

'M-404 Sh 2A 3 Makeup and Purification Unit 2 9.3-34 Sh 1 M-404 Sh 2B 2 Makeup and Purification Unit 2 9.3-34 Sh 2 M-605A 2

Chemical Addition System 9.3-40 Sh 1 M-405B 2

Chemical Addition System 9.3-40 Sh 2 M-405C 1

Chemical Addition System 9.3-40 Sh 3 M-406 Sh 1 5

Reactor Plant Sample System 9.3-3 M-406 Sh 2 5

Reactor Plant Sample System 9.3-4 M-406 Sh 3 5

Reactor Plant Sample System 9.3-5 M-406 Sh 4 5

Reactor Plant Sample System 9.3-6 M-407 Sh 1A 1 Liquid Waste Units 1 & 2 11.2-1 Sh 1 M-407 Sh 1B 2 Liquid Waste Units 1 & 2 11.2-1 Sh 2 M-407 Sh 2A 1 Liquid Waste Units 1 & 2 11.2-2 Sh 1 M-407 Sh 2B 1 Liquid Waste Units 1 & 2 11.2-2 Sh 2 4

M-407 Sh 3A 1 Liquid Waste Units 1 & 2 11.2-3 Sh 1 i

M-407 Sh 3B 1 Liquid Waste Units 1 & 2 11.2-3 Sh 2 M-407 Sh 4A 0 Radwaste Pump Seal Water System 11.2-3A Sh 1 M-407 Sh 4B 0 Radwaste Pump Seal Water System 11.2-3A l

Sh 2 M-408 Sh 1 10 Boron Recovery Units 1 & 2 9.3-35 8

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continurd)

P& ids Bechtel FSAR Dwq No.

Rev.

Title s Fig. No.

"I'M-408 Sh 2A 1 Boron Recovery Units 1 & 2 9.3-36 Sh 1 M-408 Sh 2B 1 Boron Recovery Units 1 & 2 9.3-36 Sh 2 M-408 Sh 3A 1 Boron Recovery Units 1 & 2 9.3-37 Sh 1 M-408 Sh 3B 1 Boron Recovery Units 1 & 2 9.3-37 Sh 2 M-408 Sh 4A 1 Boron Recovery Units 1 & 2 9.3-38 Sh 1 M-408 Sh 4B 2 Boron Recovery Units 1 & 2 9.3-38 Sh 2 M-408 Sh 5 7

Boron Recovery Unit 1 & 2 Riser Diagram 9.3-18 M-408 Sh 6 7

Boron Recovery Unit 1 & 2 Riser Diagram 9.3-19 M-409A 4

Radwaste Gas - Unit 1 & 2 11.3-2 Sh 1 M-409B 4

Radwaste Gas - Unit 1 & 2 11.3-2 Sh 2 M-410 12 Decay Heat Removal and Core Flooding -

5.4-10 Unit 1 M-411 12 Decay Heat Removal and Core Flooding -

5.4-11 Unit 2 M-412A 3

Reactor Building Spray Unit 1 6.2-51 Sh 1 M-412B 5

Reactor Building Spray Unit 1 6.2-51 Sh 2 M-413A 2

Reactor Building Spray Unit 2 6.2-52 Sh 1 M-413B 4

Reactor Building Spray Unit 2 6.2-52 Sh 2 M-414A 3

Fuel Pool Cooling and Purification 9.1-1 Sh 1 9

Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continusd)

P& ids i

Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

,M-414B 1

Fuel Pool Cooling and Purification 9.1-1 i

Sh 2 M-415 2

Reactor Cavity Flooding M-416 Sh 1A 3 Component Cooling Water Unit 1 9.2-7 Sh 1 M-416 Sh 1B 3 Component Cooling Water Unit 1 9.2-7 Sh 2 M-416 Sh 2A 2 Component Cooling Water Unit 1 9.2-8 Sh 1 M-416 Sh 2B 2 Component Cooling Water Unit 1 9.2-8 Sh 1 M-417 Sh 1A 3 Component Cooling Water Unit 2 9.2-9 Sh 1 M-417 Sh 1B 3 Component Cooling Water Unit 2 9.2-9 Sh 2 M-417 Sh 2A 2 Component Cooling Water Unit 2 9.2-10 Sh 1 M-417 Sh 2B 2 Component Cooling Water Unit 2 9.2-10 Sh 2 M-418A 2

Service Water Cooling Tower and Pump 9.2-2 Structure Units 1 & 2 Sh 1 M-418B 2

Service Water Cooling Tower and Pump 9.2-2 Structure Units 1 & 2 Sh 2 M-419A 2

Service Water Reactor and Auxiliary 9.2-3 Building Units 1 & 2 Sh 1 4

M-419B 2

Service Water Reactor and Auxiliary 9.2-3 Building Units 1 & 2 Sh 2 M-420 Sh 1A 2 Service Water Turbine Building -

9.2-4 Units 1 & 2 Sh 1 M-420 Sh 1B 3 Service Water Turbine Building -

9.2-4 Units 1 & 2 Sh 2 4

10 Revision 34 6/81 e

MIDLAND PLANT REFEPENCE DRAWINGS INDEX (continued)

P& ids i

Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

~q.

i M-420 Sh 2 8

Service Water Turbine Building -

9.2-5 Units 1 & 2 M-421 Sh 1 3

Reactor Building Penetration 6.8-3 Pressurization - Unit 1 M-421 Sh 2 2

Reactor Building Penetration 6.8-4 Pressurization - Unit 1 M-421 Sh 3 2

Reactor Building Penetration 6.8-5 Pressurization - Unit 1 M-422 Sh 1 3

Reactor Building Penetration 6.8-6 Pressurization - Unit 2 M-422 Sh 2 2

Reactor Building Penetration 6.8-7 Pressurization - Unit 2 M-422 Sh 3 2

Reactor Building Penetration 6.8-8 Pressurization - Unit 2 M-423 7

CCW and CRDM Interface 3.9-4 M-424 7

Control, Rod Drives, and Miscellaneous Reactor, Coolant, PP, Conn. Unit 2.

M-425 Sh 1 5

Solid Waste 11.4-1 M-425 Sh 2 3

Solid Waste System 11.4-2 Sh 1 M-425 Sh 3 1

Solid Waste System 11.4-2 Sh 2 M-425 Sh 4 2

Solid Waste System 11.4-2 Sh 3 M-425 Sh 5 2

Solid Waste System 11.4-2 Sh 4 M-426 5

Boric Acid Evaporator 9.3-39 M-427 5

Liquid Waste Evaporator 11.2-4 M-428A 3

Makeup Demineralizer 9.2-11 Sh 1 11 Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continund)

P& ids i

Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

gM-428B 3

Makeup Demineralizer 9.2-11 i

Sh 2 M-428C 3

Makeup Demineralizer 9.2-11 Sh 3 M-429 Sh 1 2.

Evaporator Plant Sample System 9.3-15 M-429 Sh 2 2

Evaporator Plant Sample System 9.3-16 M-429 Sh 3 3

Evaporator Plant Sample System 9.3-17 Sh 1 M-429 Sh 4 2

Evaporator Plant Sample System 9.3-17 Sh 2 M-430 Sh 1A 2 Auxiliary Steam Boiler System 10.4-26 Sh 1 M-430 Sh 1B 3 Auxiliary Steam Boiler System 10.4-26 Sh 2 M-430 Sh 2 3

Auxiliary Steam Boiler System 10.4-27 M-430 Sh 3A 1 Auxiliary Steam Boiler System 10.4-28 Sh 1 M-430 Sh 3B 1 Auxiliary Steam Boiler System 10.4-28 Sh 2 M-431 Sh 1A 2 Main Steam Supply System - Unit'l 10.3-1 Sh 1 M-431 Sh 1B 0 Main Steam Supply System - Unit 1 10.3-1 Sh 2 M-431 Sh 2A 0 Main Steam Supply System - Unit 1 -

10.3-2 Later Sh 1 M-431 Sh 2B 0 Main Steam Supply System - Unit 1 -

10.3-2 Later Sh 2 M-432 Sh 1A 2 Main Steam Supply System - Unit 2 M-432 Sh 1B 2 Main Steam Supply System - Unit 2 M-432 Sh 2A 1 Main Steam Supply System - Unit 2 -

Later 12 Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continutd)

P& ids Bechtel FSAR Dwg No.

Rev.

Title '

Fig. No.

.y.

1 M-432 Sh 2B 1 Main Steam Supply System - Unit 2 -

Later M-433A 2

Auxiliary Steam System - Unit 1 10.4-1 Sh 1 M-433B 2

Auxiliary Steam System - Unit 1 10.4-1 Sh 2 M-434A 2

Auxiliary Steam System - Unit 2 10.4-2 Sh 1 M-434B 2

Auxiliary Steam System - Unit 2 10.4-2 Sh 2 M-435 2

Reactor Cavity Flooding M-436 Sh 1A 2 Turbine Extraction, Heater Vents and 10.2-1 Drains - Unit 1 Sh 1 M-436 Sh 1B 2 Turbine Extraction, Heater Vents and 10.2-1 Drains - Unit 1 Sh 2 M-436 Sh 2A 1 Turbine Extraction, Heater Vents and 10.2-2 Drains - Unit 1 Sh 1 M-436 Sh 2B 1 Turbine Extraction, Heater Vents and 10.2-2 Drains - Unit 1 Sh 2 M-437 Sh 1A 3 Turbine Extraction, Heater Vents and 10.2-3 Drains - Unit 2 Sh 1 M-437 Sh IB 3 Turbine Extraction, Heater Vents and 10.2-3 j

Drains - Unit 2 Sh 2 M-437 Sh 2A 2 Turbine Extraction, Heater Vents and 10'.2-4 Drains - Unit 2 Sh 1 M-437 Sh 2B 2 Turbine Extraction, Heater Vents and 10.2-4 Drains - Unit 2 Sh 2 M-438 Sh 1A 3 Condensate and Feedwater System - Unit 1 10.4-8 Sh 1 M-438 Sh 1B 2 Condensate and Feedwater System - Unit 1 10.4-8 Sh 2 13 Revision 34 6/81 l

l l

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continutd)

P& ids Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

i M-435 Sh 2A 2 Condensate and Feedwater System - Unit 1 10.4-9 i

Sh 1 M-438 Sh 2B 1 Condensate and Feedwater System - Unit 1 10.4-9 Sh 2 M-438 Sh 3A 4 Condensate and Feedwater System - Unit 1 10.4-10 Sh 1 M-438 Sh 3B 5 Condensate and Feedwater System - Unit 1 10.4-10 Sh 2 M-438 Sh 4 2

Condensate and Feedwater System - Unit 1 10.4-10 Sh 3 M-439 Sh 1A 4 Condensate and Feedwater System - Unit 2 10.4-11 Sh 1 M-439 Sh 1B 2 Condensate and Feedwater System - Unit 2 10.4-11 Sh 2 M-439 Sh 2A 3 Condensate and Feedwater System - Unit 2 10.4-12 Sh 1 M-439 Sh 2B 1 Condensate and Feedwater System - Unit 2 10.4-12 Sh 2 M-439 Sh 3A 4 Condensate and Feedwater System - Unit 2 10.4-13 Sh 1 M-439 Sh 3B 5 Condensate and Feedwater System'- Unit 2' 10.4-13 Sh 2 M-439 Sh 4 2

Condensate and Feedwater System - Unit 2 10.4-13 Sh 3 M-440A 3

Condensate Demineralizer System - Unit 1 10.4-4 Sh 1 M-440B 3

Condensate Demineralizer System - Unit 1 10.4-4 Sh 2 M-441A 1

Condensate Demineralizer System - Unit 1 10.4-5 a

Sh 1 M-441B 2

Condensate Demineralizer System - Unit 1 10.4-5 Sh 2 4

i 14 Revisica 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continusd)

~

P& ids Bechtel FSAR Dwg No.

Rev.

Title '

Fig. No.

g.

I M-442A.

2 Condensate Demineralizer System - Unit 2 10.4-C-Sh 1 M-442B 2

Condensate Demineralizer System - Unit 2 10.4-6 Sh 2 M-443A 1

Condensate Demineralizer System - Unit 2 10.4-7 Sh 1 M-443B 3

Condensate Demineralizer System - Unit 2 10.4-7 Sh 2 M-444A 1

Feedwater Chemical Addition System 10.4-25 Sh 1 M-444B 2

Feedwater Chemical Addition System 10.4-25 Sh 2 M-445 Sh 1 3

Steam Plant Sample System 9.3-7 M-445 Sh 2 3

Steam Plant Sample System 9.3-8 M-445 Sh 3 3

Steam Plant Sample System 9.3-9 M-445 Sh 4 3

Steam Plant Sample System 9.3-10 M-445 Sh 5 3

Steam Plant Sample System 9.3-11 M-445 Sh 6 3

Steam Plant Sample System 9.3-12 M-445 Sh 7 3

Steam Plant Sample System 9.3-13 M-445 Sh 8 3

Steam Plant Sample System 9.3-14 M-446A 3

Circulating Water - Units 1 & 2 10.4-3 Sh 1 M-446B 3

Circulating Water - Units 1 & 2 10.4-3 Sh 2 M-446C 1

Circulating Water - Units 1 & 2 10.4-3 Sh 3 M-447 Sh 1A 3 Service Water, and Circulating Water Chemical Addition M-447 Sh 1B 3 Service Water, and Circulating Water Chemical Addition 15 Revision 34 6/81 i

,,--c-

-m--

m-

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

s

" M-447 Sh 2 4

Circulating Water and Service Water Chemical Addition 5

l M-447 Sh 3A 3 Circulating Water and Service Water Chemical Addition M-447 Sh 3B 3 Circulating Water and Service Water Chemical Addition M-448 Sh 1 7

Instrument and Service Air 9.3-1 M-448 Sh 2 9

Instrument and Service Air 9.3-2 M-449 Sh 1A 4 Plant Water Storage and Transfer 9.2-18 Sh 1 M-449 Sh 1B 3 Plant Water Storage and Transfer 9.2-18 Sh 2 M-449 Sh 2 7

Plant Water Storage and Transfer 9.2-19 M-450 8

Lube Oil Unit 1 M-451 8

Lube Oil Unit 2 M-452 Sh 1A 3 Emergency Diesel Engine Oil Storage 9.5-25 and Transfer System Sh 1 M-452 Sh 1B 3 Emergency Diesel Engine Oil Storage 9.5-25 and Transfer System Sh 2 M-452 Sh 2 0

Diesel Fuel Oil Storage and Transfer 9.5-25 Yard Lighting Diesel and UPS Facility Sh 3 M-453 7

HVAC Reactor Building Unit 1 9.4-10 M-454 sh 1 6

HVAC Auxiliary Building Units 1 & 2 9.4-3 M-454 Sh 2 4

HVAC Auxiliary Building Units 1 & 2 9.4-4 M-454 Sh 3 5

HVAC Auxiliary Building Units 1 & 2 9.4-5 M-454 Sh 4 3

HVAC Auxiliary Building Units 1 & 2

'9.4-6 M-454 Sh 5 6

HVAC Auxiliary Building Units 1 & 2 9.4-7 M-454 Sh 6 0

HVAC Auxiliary Building Units 1.& 2 9.4-7A 16 Revision 34 6/81 r,

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR

. Fig. No.

Dwg No.

Rev.

Title s

44 1,M-455 Sh 1 3

HVAC Turbine Building Unit 1

-9.4-8 M-455 Sh 2 3

HVAC Turbine Building Unit 2 9.4-9 M-456 Sh 1A 2 Plant Heating Turbine Building 9.4-13 Sh 1-M-456 Sh 1B 0 Plant Heating Turbine Building 9.4-13 Sh 2 M-456 Sh 1C 0 Plant Heating Turbine Building 9.4-13 Sh 3 M-456 Sh 2A 2 Plant Heating Auxiliary and Reactor 9.4-14 Buildings Sh 1 M-456 Sh 2B 2 Plant Heating Auxiliary and Reactor 9.4-14 Buildings Sh 2 M-456 Sh 3A 2 Plant Heating Office and Service 9.4-15 Sh 1 Buildings M-456 Sh 3B 1 Plant Heating Office and Service 9.4-15 Buildings Sh 2 M-456 Sh 4 4 Plant Heating Miscellaneous Structures 9.4-16 M-457 Sh 1A 1 Chilled Water Auxiliary Building 9.2-20 Sh 1 M-457 Sh 1B 1 Chilled Water Auxiliary Building 9.2-20 Sh 2 M-457 Sh 2A 4 Chilled Water Safeguard Equipment Unit 1 9.2-24 Sh 1 M-457 Sh 2B 3 Chilled Water Safeguard Equipment Unit 1 9.2-24 Sh 2 M-457 Sh 3A 3 Chilled Water Safeguard Equipment Unit 2 9.2-25 Sh 1 M-457 Sh 3B 4 Chilled Water Safeguard Equipment Unit 2 9.2-25 Sh 2 M-457 Sh 4A 1 Chilled Water Turbine Building Unit 1 9.2-21 l

Sh 1 1

17 Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (centinued)

P& ids Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

M-457-Sh 4B O Chilled Water Turbine Building Unit 1 9.2-21 Sh 2 M-457 Sh SA 2 Chilled Water Turbine Building Unit 2 9.2-22 Sh 1 M-457 Sh 5B 0 Chilled Water Turbine Building Unit 2 9.2-22 Sh 2 M-457 Sh 6 6

Chilled Water Office and Service 9.2-23 Buildings M-458 Sh 1A 2 Fire Protection 9A-30 Sh 1 M-458 Sh 1B 3 Fire Protection 9A-30 Sh 2 M-458 Sh IC 3 Fire Protection 9A-30 Sh 3 M-458 Sh 2 3

Fire Protection 9A-30 Sh 4 M-459 Sh 1A 2 Domestic Water 9.2-12 Sh 1 M-459 Sh IB 2 Domestic Water 9.2-12 Sh 2 M-459 Sh 2 5

Domestic Water 9.2-12 Sh 3 M-459 Sh 3 4

Domestic Water 9.2-12 Sh 4 M-460 Sh 1 6

Process Steam, Supply and Return System 10.4-20 M-460 Sh 2A 1 Process Steam, Supply and Return System 10.4-21 Sh 1 M-460 Sh 2B 2 Process Steam, Supply and Return System 10.4-21 Sh 2 M-460 Sh 3A 2 Process Steam, Supply and Return System 10.4-22 Sh 1 4

18 Revisicr, 34 6/81 1

l

' MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR Dwq No.

Rev.

Title Fig. No.

i q.

I M-460 Sh 3B 1 Process Steam, Supply and Return System 10.4-22 Sh 2 M-460 Sh 4 4

Process Steam, Supply and Return System 10.4-22A M-461 Sh 1A 2 Process Steam Evaporator System 10.4-14 Sh 1 M-461 Sh 1B 1 Process Steam Evaporator System 10.4-14 Sh 2 M-461 Sh 2A 3 Process Steam Evaporator System 10.4-15 Sh 1 M-461 Sh 2B 2 Process Steam Evaporator System 10.4-15 Sh 2 M-461 Sh 2C 0 Process Steam Evaporator System 10.4-15 Sh 3 M-461 Sh 3A 2 Process Steam Evaporator System 10.4-16 Sh 1 M-461 Sh 3B 1 Process Steam Evaporator System 10.4-16 Sh 2 M-461 Sh 4A 1 Process Steam Evaporator System 10.4-17 Sh 1 M-461 Sh 4B 1 Process Steam Evaporator System 10.4-17 Sh 2 M-461 Sh SA 1 Process Steam Evaporator System 10.4-18 Sh 1 M-461 Sh SB 2 Process Steam Evaporator System 10.4-18 Sh 2 M-461 Sh 6 5

Process Steam Evaporator System 10.4-19 M-461 Sh 7 4

Process Steam Evaporator System 10.4-19 Sh 1 M-461 Sh 8 2

Process Steam Evaporator System 10.4-19 Sh 2 M-462 7

HVAC - Reactor Building 9.4-10A 19 Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR I

Dwg No.

Rev.

Title Fig. No.

s

" M-463'Sh 1A 3 Miscellaneous Gas System Hydrogen Supply 9.3-41 Sh 1 i

M-463 Sh 1B 3 Miscellaneous Gas System Hydrogen Supply 9.3-41 Sh 2 M-463'Sh 2A 2~

Miscellaneous Gas System Carbon Dioxide 9.3-43 4

l Supply Sh 1 1

l M-463 Sh 2B 2 Miscellaneous Gas System Carbon Dioxide 9.3-43 Supply Sh 2 1

M-463 Sh 3 3

Miscellaneous Gas System Nitrogen Supply 9.3-42 l

M-464 6

Cooling Pond Blowdown and Makeup System 10.4-24 M-465 Sh 1 5

HVAC - Control Room-Battery Room-Switch-9.4-1 gear and Cable Spreading Room M-465 Sh 2 5

HVAC - Control Room-Battery Room-Switch-9.4-2 gear and Cable Spreading Room M-466 6

HVAC Access Control and Computer Area 9.4-12 M-467 Sh 1 1

HVAC Office and Service Buildings 9.4-17 M-467 Sh 2 1

-HVAC Office and Service Buildings 9.4-18 i

Sh 1 M-467 Sh 3 1

HVAC Office and Service Buildings 9.4-18 Sh 2 l

M-468 Sh 1 3

HVAC Diesel, Generator Building and 9.4-11 Service Water Pump Structure M-468 Sh 2 2

Miscellaneous Structures HVAC 9.4-20 i

j M-468 Sh 3A 1 Miscellaneous Building HVAC System j

(Evaporator and Auxiliary Boiler Building)-

M-468 Sh 3B 1 Miscellaneous Building HVAC System (Evaporator and Auxiliary Boiler Building)

M-468 Sh 4 2

Miscellaneous Structure HVAC 9.4-21 (Guardhouse) 20 Revision 34 6/81

MIDLAND PLANT REFERENCE DRAWINGS INDEX (continued)

P& ids Bechtel FSAR Dwg No.

Rev.

Title Fig. No.

i

~

2 Miscellaneous Structure HVAC 9.4-22 M-468 Sh 5 M-468 Sh 6 0

Miscellaneous Structure HVAC 9.4-22 Sh 1 i

M-469A 3

Boron Recovery Degasifier 9.3-45 Sh 1 M-469B 3

Boron Recovery Degasifier 9.3-45 Sh 2 M-470 Sh 1A 3 Chemical and Oily Waste System 9.5-30A

/

M-470 Sh IB 3 Chemical and Oily Waste System 9.5-30B M-470 Sh 2A 3 Chemical Waste System 9.5-29 Sh 1 M-470 Sh 2B 3 Chemical Waste System 9.5-29 Sh 2 i

M-472 Sh 1 1

Miscellaneous Instrumentation Reactor 6.2-119 Building Unit 1 M-472 Sh 2 1

Miscellaneous Instrumentation Reactor 6.2-120 Building Unit 2 M-478 Sh 1 1

Preliminary Process Steam Radiation 11.6-1 Monitoring On-Line Monitoring System Sh 1 M-478 Sh 2 1

Preliminary Process Steam Radiation 11.6-1 Monitoring On-Line Monitoring System Sh 2 M-478 Sh 3 1

Preliminary Process Steam Radiation 11.6-1 Monitoring On-Line Monitoring System Sh 3 M-478 Sh 4 1

Preliminary Process Steam Radiation 11.6-1 Monitoring On-Line Monitoring System Sh 4 i

21 Revision 34 i

6/81 i

l

,e A

4 p

s I

R. Budwani Rules Court West,12W Route 46 Lodi, N. J.

07644 December 18, 1981

Dear Sir:

It is my understanding that the CASE LOAD FORECAST PANEL visited the construction site of the following nuclear unit during 1981.

Plant:

I (d Cm kIL Applicant: OGwww',

vs Docket No.:

To -.12h,f R

[em Y 6N&v As licensing Projbct-Manager for this project, I shall be highly obliged if you can kindly arrange to send me a copy of the applicant's presentation ~*and the summary of NRC's evaluation for the above nuclear project.

Your cooperation and help will be deeply appreciated. The inconveni-ence caused is regretted.

With compliments and thanks.

i Very truly yours, ML' j

f R. N. Budwani l

RNB/mm I

l y

u-2.s-u,tui l

Y? '^ 3 W 53

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