ML19326D242

Amend 25 to Applications for CP & Ol,Consisting of Revised & Addl Pages & Figures for Incorporation Into Psar. Analyzes Postulated High Energy Pipe Rupture Outside Reactor Bldg

ML19326D242
Person / Time
Site:	Midland
Issue date:	02/01/1974
From:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19326D236	List: ML19326D235 ML19326D242
References
NUDOCS 8006090672
Download: ML19326D242 (6)

Text

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5511C O'. FEB 4 %74 i IS nuan31 6l CONSUMERS POWER COMPANY tut =tip tt, tut ctut

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APPLICATION FOR

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ll REACTOR CONSTRUCTION PERMIT AND OPERATING LICENSE 21/ g

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Docket No. 50-329 7

PE3 4 374 Docket No. 50-370 g

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ca Amendment No. 25

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Enclosed herewith, amerding and supplementing the above entitled application are revised and additional pcges and figures for incorporation in the Preliminary Safety Analysis Report submitted with the original application on January 13, 1969, as amended. This 72aterial consists of the following:

1.

An analysis of high energy pipe ruptures outside the reactor building. This analysis is based upon the enclosure to A. Giambusso's letter dated December 15,1972, " General Information Required for Considcration of the Ef fects of a Piping System Break Outside Contain=er.," as modified by errata dated January 18, 1973. Wherever practical, this basic criteria is supplemented by the criteria for new plants as attached to J. F. O' Leary's letter dated July 12, 1973.

The analysis and aseociated material is included in the rollowing:

(a) A new section 14.4, Analysis of High Energy Pipe Rupture Outside the Reactor Building, which contains the analysis of the effects of postulated high energy pipe ruptures in the main steam, main reedwater, and auxiliary feedwater systems.

(b) A new Appendix !I, Design Features for High Energy Pipe 80.06090

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2 Failure Outside the Reactor Building, which summarizes the structural design features provided for protection from postulated high energy line breaks described in Section 14.4 above.

(c) A revised page 14-21 and new page.14-21a containing a new Section 14.1.2.11, Main Feedwater Line Failure.

(d) A new page 7-8a containing new Sections 7.1.2.2.3 and 7.1.2.2.4 which concern the instrumentation and controls associated with the main steam isolation system and automatic starting of the auxiliary feedwater system, respectively.

4 (e) A revised page 10-4 to add reference to the new Section 7.1.2.2.3 under Section 10.3.1.

(f) New Figures 10-1, 10-2 and 10-2a to replace existing Figures 10-1 and 10-2.

Figure 9-10 is deleted.

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(g) Revised equipment location drawingc c<.asisting of Figures 1-2 through 1-7,1-9 through 1-12c and 1-16 through 1-19.

These figures replace existing Figures 1-2 through 1-7, 1-9 through 1-12 and 1-16 through 1-18.

2.

Revised pages 5-45 and 5-46 which clarify the reinforcing steel testing requirements for both the supplier and the user.

3.

A revised page 2-8 and new Figure 2-16, 2-16a, and 2-16b de-tailing the design of the makeup water intake structures.

This structure has been mod.iied to limit the intake flow velocity to a maximum of 1 foot /

second in accordance with the additional conditions specified in canstruction Permits No.'s CPPR-81 and CPPR-82.

4.

Revised pages 9-18, 9-23, 9-24, and 9-35 and revised Figures 9-6 and 9-9 to ceflect the use of the Service Water System in place of the Fire Protection System as the backup water supply for the auxiliary feedwater system and the fuel pool cooling system.

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I the AEC-DRL Staff Safety Evaluation, page 14, cad supercedes the report "Maximuu Flood Conditions at M(dland, Michigan" which was submitted by cmendment No. 6 (dated December 29, 1969) and the undated report presented to the AEC informally ou May 4, 1970. The updating of previous supplied PSAR information reflecting the new PMF report will be supplied with a future amendment.

As discussel in the meeting with the AEC Staff an September 11, 1973,

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there are several changes in the design of 'the Midland plant which will not be submitted in the f arm of an amendment to the Preliminary Safety Analy tas Report. Those changes are consfdered to be an upgrade in the design of the plant and therefore we do not consider AEC review prior to submittal of the Final Safety Analysis Report necessary.

A list of these changes is as follows:

1.

The electrical power system at the Midland Plant has been changed f

to include 4 diesel generator sets, each with a 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3100 KW.

Two generator sets will supply cach reactor unit.

2.

The DC portion of the electrical power system has been changed to consist af the following:

(a) One 250 volt center tapped battery per reactor unit to supply the 250 volt and 125 volt balance of plant loads.

(b) Four 125 volt batteries, two per reactor unit, to supply the class IE loads.

(c) One inverter per reactor unit for the plant computer.

(d)

Four inverters per reactor unit for class lE and vital AC loads.

3.

The 138 kV supply lines to the Midland Plant Startup Transformers have been changed. The transformers will now be supplied from separate sources

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5.

Revised pages 1.4-1 and 9.5-1 amending the responses given in Amendment No. 5 (dated November 7,1969) as amended in Amendment No. 6 (dated December 29, 1969), to the items listed in Enclosure A to Dr. Peter A. Morris' letter to Mr. R. D. Allan dated September 26, 1969.

These revised pages delete the Seismic Category 1 design of the fire protection system.

Figure 9.5-1 is deleted.

6.

Revised pages 1C-3, 7-3, and C-14 which correct various typographical errors.

7.

Revised pages vii, x, xiv, xv, 1-17, 1B-iv, 2-v, 2A-v, 5-v, 6-1,10-11, and 14-1, and new pages 1-iva,14-ia,14-iia, & 14-viii which update the various Tables of Contents to reflect current material and page numbers.

8.

A revised page 13.7.I.2-1 amending the response given in Amendment No. 5 (dated November 7,1969) to the items listed in Enclosure A to Dr. Peter A. Morris' letter to Mr. R. D. Allen dated September 26, 19o9.

9.

Revised pages 6.16-1 and 7-1, and new Figures B-7-1 & B-7-2 atending the responses given in Amendments No. 5 (dated November 7,1969), No. 6 (dated December 29, 1969), and No. 7 (dated January 30, 1970) to the items listed in Enclosure B to Dr. Peter A. Morris' letter to Mr. R. D. Allen dated September 26, 1969.

Figure B-7 is deleted.

These new and revised pages bear the notation " Amendment No. 25, 2/74".

Except for the new Section 14.4 and the new Appendix 51, the pages are marked in the margin to indicate where changes have been made.

Also enclosed is a report entitled " Probable Maximum Flooding near the Midland site" prepared by Bechtel dated January 1974, Revision 1.'

This report was prepared in response to the comments contained in

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via separate circuits and towers. The two sources will be the Tittabawassee Substation and the Dow South Substation.

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The design of the Borated Water Storage Tanks has been changed to consist of 2 tanks, one per reactor unit.

It is requested that the staff review of item 9 of this amendment be completed by April 1, 1974, to permit us to finalize design of the j

containment sump recirculation line to meet construction schedule. We ruquest that staff review of the remainder of the amendment be completed by August 1, 1974 CONSUMERS POWER COMPANY

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_o Dated February 1, 1974 Stephen H. Howell, Vice President Sworn and subscribed to before me on this 1st day of Februsry, 1974.

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Notary hblic, Jackson Cmnty, Michigan My canaission expires May 18, 1976

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AEC DISTP~UTICN FOR PART 50 DOCKET MATER ~ i (TDiPORARY FORM)

CONTROL NO:

960 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Crnsumers Power Company Jackson, Michigan Steohe H. Howe 611 2-1-74 2-4-74 X

TO ORIG CC OTIER SENT AEC PDR XXX J

SENT LOCAL PDR XXX J. F. O'Learv 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

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XXX 1

_GO-329330 DESCRIPTION:

ENCLOSU?IS:

Ltr trans the following.....

AMDT #25 to the PSAR notarized 2-1-74

• • Denotes Letter Only consisting of revised and additional pages, NOTE: Letter indicates that certificate of tables and figs tothe PSAR f_

,7f service enclosed...not received as of p**~/

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2-6-74 7DQNOT hiOYE Ir CKNOWLEDGED j

'A PLANT NAME: MIDLAND 1 & 2 (3 siened/67 cys encl ree'd)

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