ML19329F429
| ML19329F429 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Midland, Shoreham  |
| Issue date: | 09/30/1970 |
| From: | Price H US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Bauser E CONGRESS (JOINT & ROTATING COMMITTEES, ETC.) |
| Shared Package | |
| ML19329F430 | List: |
| References | |
| NUDOCS 8006270471 | |
| Download: ML19329F429 (1) | |
Text
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' fo 3 7f SEP 3 01970 Mr. Edward J. Batuser Executive Director Joint Comunittee on Atomic Energy Congress of the United States
Dear Mr. Bauser:
Esports of the Advisory Committee on Reactor Safe-guards, dated September 23, 1970, concerning Indian Point Nuclear Generating Unit No. 2, Shoreham Nuc1 car Power Station Unit 1, and Midland Plant Unita 1 and 2, are enclosed for the information of the Joint Committee.
Sincerely, Original Signed by Chris L. Heng,,,cn Harold L. Price Director of Regulation
Enclosures:
As stated i
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Cong. Relations (2)
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Form AEC-318 (Rev.9-53) AICM 0240
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ADVISORY COh ITTEE ON REACTOR SAFEGUA' S
llNITFD STATES ATOMit' ENERGY COMMISSION WASHINGTON. D.C. 20545 September 23, 1970 Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Commission Washington, D. C.
20545
Subject:
SUPPLEMENTAL REPORT ON MIDLAND PLANT UNITS 1 AND 2
Dear Dr. Seaborg:
At its 125th meeting, September 17-19, 1970, the Advisory Committee on Reactor Safeguards completed its review of amendments to the application by the Consumers Power Company to construct the Midland Plant Units 1 and 2.
This project,was the subject of a report to you dated June 18, 1970. The review was reopened in consideration of additional submittals by the applicant proposing an increase in the' design pressure of the containment structure and the addition of a system of reboilers for the generation qf steam to be exported to the Dow Chemical Company. These changes were consideged at a Subcommittee meeting held in Washington, D. C. on September 14, 1970. The Committee had the benefit of discussion with representatives and consultants of the Consumers Power Company, Babcock and Wilcox Company, Bechtel Corporation,'Dow Chemical Company, and the AEC Regulatory Staff. The committee also had the benefit of the documents listed.
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The applicant has rc~ised downward his estimate of the free volume and v
internal surface area of the containment structure and has revised upward to 60 psig th;e calculated peak containment pressure reached in
," the unlikely event of a loss of coolant accident. The contai,nment design pressure has:bcen raised to 67 psig to provide a suitable margin above the peak accident pressure, and an increas.ed number of'prestress-ing tendons will be!provided in the containment structure to accommodate the increased pressure. No changes in the structural design criteria are proposed. The Committee believes these changes are sat!sfactory.
In the earlier design the export steam was taken from the secondary side of.the main steam generators and might contain traces of radioactive leakage from the primary system. The applicant now proposes to use this steam in a system of shell and tube reboilers to generate tertiary steam for export to the Dow Chemical Company. Secondary steam condensate from the reboilers'is returned to the turbine condenser hot well while feed water for the tertiary side of the reboilers is supplied by con-
- densate from-the tet.tiary steam which is supplemented as required by W) u 0
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aepu.moca-2 3, tv /u demineral'ized' water from Lake Huron.. Blowdown from the reboilers is
.normally routed to the Dow waste treatment system for disposal to the river but may be sent'to the radwaste system of the nuclear plant.if secondary to tertiary leakage is detected.
The applicant proposes to install monitoring and analytical facilities to determine the levels of radioactivity in the export
- steam as described in the June 18, 1970, letter; these include an on-line analyzer for gamma activity and sensitive low level beta counting equipment for analysis of sampics of the condensed steam. The applicant expects that the tertiary steam delivered to Dow will contain no more radioactivity than the treated make-up water from Lake Huron. Recycling tertiary steam condensate may
'rcsult in some slight concentration of naturally occurring radioact4vity in the reboiler system but is not expected to effect the validity of the comparison between steam and make-up water radioactivity.as a sensitive indication of leakage in the reboilers. If detcetable leakage occurs, corrective action will be taken in the plant or delivery of export steam will be terminated.
The applicant agrees to demonstrate the analytical equipment and pro-cedures in development programs to be carried forward during construction of the Midland Plant.
The Committee believes that the proposed system of reboilers will provide substantial additional assurance that leakage of primary system radio-activity.into the export steam can be maintained at an axtremely low and insignificant level and that the export steam can be maintained essentially at natural background IcVels. The detailed procedures for monitoring and control of the roboiler system should be developed during construction in a manner satisfactory to the Regulatory Staff. The Committee wishes
,to be kept informed.
The Committee believes that the above items can be resolved during con-struction and if due consideration is~given to these items and to the items referred to in its June 18, 1970 report, the nuclear units proposed for'the Midland Plant can be constructed with reasonable assurance that they can be operated without undue risk to the health and safety of the public.
Sincerely yours,
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Joseph M. Hendrie Chairman References
- 1) L Amendments 14-18 to the License Application 1,
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