ML17037B859
| ML17037B859 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/26/1973 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B859 (6) | |
Text
Docket No. 5Q-410 JUL 36 197'oss A. Moore, Assistant Director for Boiling Mater Reactors, L
THRU:
Robert A. Clark, Chief, Gas Cooled Reactors
- Branch, L Original,signed by
SUMMARY
OF ACRS MEETING, NINE MILE POINT-2 Robert A. Clark Representatives of Niagara Mohawk Power Corporation, Stone 8 Mebster Engineering Corporation, and General Electric Company met with the ACRS and.the Regulatory staff on July 12, 1973 concerning Niagara Mohawk Power Corporation's application for a construction permit for the Nine Mile Point Nuclear Station, Unit 2.'he meeting was open to the public except for a closed session in which the subject of industrial security was discussed.
A transcript of the meeting was prepared by Ace-Federal Reporters, Incorporation; copies of which are available in the public document rooms and in the AEC's Bethesda Library.
On July 17, 1973,- the ACRS reported by letter to Chairman Ray on the Nine Mile Point-2 facility.
A copy of this letter fs appended to this report.
The various items discussed at the meeting are, summarized below in the. order fn whfch they were first considered at the meeting.
1.
Flood Protection a
The 'staff ndicated that there is a difference of predicting
- the maximum surge between the applicant and the staff of 3 feet (251 and 254 ft LSD,'espectively).
The app1fcant fs continuing his study using a 2-D model developed by his Architect-Engineer.
It was indicated that the results from this study will be reviewed by the staff prior to construction of the dike and drainage system.
{b)
The applicant-has described dn fntergeptor ditch behind the dike with the capacity of 200,000 ft.
The staff does not agree with the interceptor ditch capacity and will require
,substantiation to-show that the design capacity fs sufficient to avert any flooding that could adversely affect any safety-related structures or systems prior to the construction of the dike and drainage system.
2.
Criteria Utilized to Ascertain the ECCS The appl cant presented results of ana yses performed for different type of pipe breaks utilizing a stretch power of 3,489 MMt which is 5 percent above the designed power.
All analyses showed that the OFFICE >
SURNAhIE >
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the maximum clad temperature were below the 1971 Interim Acceptance Criteria of 2300'F.
Although the interim criteria were met, the ACRS committee queried the applicant relative to his ECCS improvements as stipulated by the ACRS letter of January 7, 1972 and also the effects of fue't densification.
To the former question on ECCS improve-ments the applicant indicated'that the 1971 Interim Criter ia was met.
Also, the applicant was cognizant of the new proposed fuel design for, Grand)rGu'ff, and would not preclude the use of that fuel in Nine Mile Point-2 depending on the outcome of the licensing review.
Relative to fuel densification, the applicant indicated that he has submitted the generic reports on this topic and is awaiting the results of the staff's review.
3.
ADS Interlock AAdA p
ddt tht 1tf t.
th Is 1
k yt in the ADS system.
The system that has been incorporated into the Nine Hi'le Point-2 is as'follows:
to actuate the ADS system manually 2 buttons must be pushe'd which-inturn initiate a 2 minute timer which delays the valves from opening.
If no operator action is taken and
-if there is low pressure pump running (ADS system interlock); the ADS is activated.
To circumvent the ADS interlock and the timer.
each individual valve can be actuated by pushing She respective individual push button.
Hain Steam Line Isolation Valve Leaka e
he app cant descr e
a sea water system which will augment the function of the main steam line isolation valves to achieve a positive water seal.
At the staff's request the applicant is committed to perform detail thermal stress and deformation analysis.
The resu'tts will be presented at the OL stage.
In the event these studies are not conclusive, the applicant wi11 be required to conduct appropriate tests to supplement these analyses.
Combustible Gas Control e app cant n
cat that the system consists of two 1005 capacity recombiners to limit the oxygen concentration.in the containment to below the lower flammability limit following a LOCA, As a backup system a non-safety purge system is used as indicated in Regulatory Guide 1.07.
The'ystem is in the preliminary stages of design; and therefore, the type of recombiner, thermal.or catalytic, has not been selected.
6.
RHR Motor-0 crated Suction Valve Inter'tocks he ACRS comm tte was ntereste to exp ore whether the valve inter-lock in the low pressure RHR system in the primary system in this plant was the same as for other General Electric plants which have recently received construction permits.
The applicant indicated in the affirmative;
- however, a difference did exist for the interlock system of this plant in that the designed intent was to meet the diversity principle required OFFICE >
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7.
Seal S stem Between Dr and Met Mall e f na top c to e
scussed at t e meeting was relative to the seal system that exists between the drywell floor and wall for the over-under type of pressure suppression system.
It was indicated that the seal consists of two seals in series, that the seal cannot be leak tested in service, and that this seal design is the same as the Shoreham plant.
Original signed by:
Anthony Bournia ~
Anthony Bournia, Prospect Manager Gas Cooled Reactors Branch Directorate of Licensing
Enclosure:
ACRS Letter dated 7/17/73 Distribution:
-Docket File AEC PDR Loca1 PDR L Reading RP Readdng GCR Reading ED G.
Case A. Biambusso R. S; Boyd V. A. Moore RP/BCs J. Hendrie TR/ADs TR/BCs R.
F. Fra1ey, ACRS W. Haass A.'ournia J'. A. Nooris Massar/Bordenick RO,(3)
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Frahm F>> Rosa J.
E. Richardson
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E. Lipinski
. L'.
B. Riani D.
D, Rieff F. Guevara J.
E. Kohler E.
F. Hawkins F. J.
Congel OFFICE P L:GCR L:bc@
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