ML19256D263
| ML19256D263 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/18/1967 |
| From: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910170776 | |
| Download: ML19256D263 (2) | |
Text
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Roger S. Boyd, Assistant Director, ERL THRU
- Charles G. Long, Chie f, RP3-3, LRL 3rian Grimes, Reactor Project Branch :;o. 3 Division of Reactor Licensing MZZTU;G WITH METROPOLITAN EDISCN CN CCRE COOLU;G AND AMENIHENI 4 TO TE THREE MILE ISLAND APPLICATION - DOCIET 50-239 On December 14, 1967, a meeting was held in the Bethesda offices to discuss the Metropolitan Edison Cenpany's Three Mile Island applicatien. The purpose of the meeting was to discuss the revision of the core cooling systems to meet our current inter Jtation of Criterica 44 of the General Design Criteria which is that the systems provided nest be capable of withstanding (detecting and isolating) a passive failure in the recirculation mode. The applicant proposed two separate systems for core injection, two intermediate cooling loops and two service water systems. The intermediate and service water loops would be independent of the normal plant cooling syste:ns and would be used only for shutdown decay heat removal. An extra 1007 high pressure injection pump will be provided for normal makeup and maintenance capability. An extra set of pump internals and probably motor parts would be kept on site to allow quick repair of the low-pressure injection system since only one 1007. low-pressure injection pump will be provided in each system.
A failure of the sump line up to the first isolation valve will be coped with by jacketing the pipe and line including the isolation valve. Leaks in tht, remainder of the systems will be detected by providing separate routings and sumps for each system and measuring sump water levels.
We pointed out that in the proposed system there is a significant length of pipe which is common to two safety features: the core injection and the con-tainment spray. We stated that it is desirable to prevent a single passive failure from removing capacity from both features. The applicant indicated that a cross-tie wculd be provided in one of the systems to meet this objec-tion.
The new systems will require a new diesel arrangement. The proposed sche =c is two diesels, each 1007 capacity (2850 kw), one serving each injection system. The new diesel loadings and core cooling systems will ha submitted by December 22.
We suggested that the applicant look at the need for providing heat exchangers on the containment spray since if all systems functioned as designed, the building coolers might reduce the contairseent atmosphere to a lower temper-ature than the spray water and inhibit mass transfer of iodine from the air to the droplets.
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1 Roger S. Boyd 2-A nu:nber of other areas were discussed with respect to the answers contained in Amend:sent 4 submitted l>ecember 8.
The following revisions will be made to the answers by the applicant by an amend:acnt to be sub-mitted by Deceuber 22.
1.
The organization chart will be revised to indicate more clearly that the role of CPU is advisory rather than a line function.
2.
Guestion 16.4 will be revised to indicate that the loss of two check valves in the core barrel could be detected and to indicate the infomation available to the operator. A statement that flow distribution tests will be conducted on the lio scale model to decemine the effect of loss of a valve will be included. We stated that our position is that vibration tests of the valves will also be required.
3.
The answer to Questice 17.7 (steam generator leakage) will be revised to relate the doses to the design basis accident with TID releases.
4.
The answer to question 18.2 (on remote station shutdown) is satisfactory except that we required that, the decay heat purnps should have capability for remote control to provide capabi'ity to provide a cold shutdown rather than maintaining a hot system indefinitely. The applicant has taken this under advisement.
The applicant will also look into the heat transfer tests on the building fan coolers to see if the steam and condensation effects on the fan-tube bundle combination are taken into account.
Replacement pages to the application will not be provided to reflect changes in the core cooling systems because of the time schedule. We stated that the amendment with the revisions cust therefore contain enough infor-nation to stand alone.
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C. G. Long D. F. Ross P. S. Check W. R. Butler B. K. Grimes Suppl.
RP3-3/DRL Reading 1450 133
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