ML20127N571
| ML20127N571 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/01/1970 |
| From: | Vassallo D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9212010312 | |
| Download: ML20127N571 (4) | |
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ATOMIC ENERGY COMMISSION (Jg)s W ASHINGTON. D C.
20145 gg April 1, 1970 R. C. DeYoung, Assistant Director for PressurizedA) er Reactors, DRL D. K. Muller, Chief. PWR Projects Branch [/1, DRL THRU:
ITEMS WHICH MAY BE INCOMPLETE FOR MONTICELLO PL/.NT AT PROPOSED TUEL LOADING DATE At a meeting held in Bethesda on March 20, 1970 Northern States Power (NSP) and General Electric (GE) discussed with us those plant items which may not be completed in time for the proposed fuel loading date.
Fuel loading has tentatively been set by the applicant for April 25, 1970, contingent upon approval by the Atomic Safety and Licensing Board (AS&LB).
The applicant is also requesting approval for power testing up to 5 MW (t),
The matters discussed at the meeting are summarized below.
NSP indicated that although the remaining items may not be completc for initial fuel loading, all items would be completed in time for the startup tests with the vessel head on.
1.
Permanent Security Fencing t
The applicant has stated that the present construction fence is located outside the parameter of the plant permanent security fence, and thus should give essentially the same security as the permanent fence.
Until the permanent construction fence is installed, a guard will be stationed at the main gate. As an added security measure, the applicant has stated that the present construction fence is, and will be patrolled periodically by uniformed guards.
2.
Seismic Restraints The applicant han stated that Class II piping restraints may not be entirely completed for such systems as the radwaste, fuel pool cooling, servit.c water, instrument and service air, makeup and service water, and the main steamline beyond the second isolation valve. All Class I piping restraints will be completed including the restraints for the following systems: RHR, core spray, HPCI, RCIC, and the standby liquid control system. Further, the applicant has stated that all piping restraints will be installed prior to the startup tests to be conducted with the vessel head on.
No loads will be applied during fuel loading operations.
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Completion of Instrumentation Modifications _
As ; result of our review the modifications listed below were required.
These r;odifications will not be completed prior to the fuel loading.
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Provision for checking pressure switch in.the auto-relief valve ballows.
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Wida-tange vessel level recorder and transmitter (device checks level from below fuel to steam area in the reactor T
vessel).
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Modification to a-c interlock to install additional' pressure switches to meet IEEE-279. This will be completed before pulling rods with the vessel head on.
4.
Liquid Radwaste System The applicant has stated that the liquid radwaste system will be -
'I functionally complete, except for the.conveycr and drum copping system.. NSP indicated that although all the-tests to be performed on the system will not be completed the system will.be operational l
and will be used to process and hold.up radwaste generated during the fuel loading and low power testing (vessel head off).
i We expro-sed some' concern about using this system for processing
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- radwaste before the system had been completely checked out.
Although radioactivity levels should be low during fuel loading and low power testing, we asked.the. applicant to further1 describe:
just what procedures would be enforced at this time to prevent inadvertent discharge of liquid waste. NSp said_that they would. reexamine this matter and report to us in more detail.
5.
Secondary Containment Leak Rate Tests
-This leak rate test is scheduled'for the later part of April -but-
'it is possible that they will not be successfully_ completed for 3'
fuel loading. We informed the applicant-that he mus.t analyze-the radiological consequences, assuming-5 MW' operation and the non availability of-the. secondary containment.
A similar analysis was done for Dresden 2.to_ permit testing up to 5 MW without the availability of secondary containment.
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i 6.
Offsite Power Sources The applicant has stated that four of the five transmission lines that will supply power to the plant substation will be energized to serve the substation before commencement.of fuel loading.
The fif th line is scheduled to be in service about June 15, 1970. However, since the Technical Specifications permit reactor operation with a minimum of at least two transmission lines fully operational, this is not a problem.
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7.
Primary Containment Inertin'c System l
t As a result of a late' start on design and procurement following.
l resolution of the requirement for this. system. - the system will:
not be completed until commencement of full power commercial I
operation. We understand that this is essentially the same situation that occurred at the Oyster Creek facility and was -
permitted by DRL.
8.
Construction Personnel Activity We asked the applicant about restriction'of personnel activity during fuel loading and other. security measures-which'would be-
- i in1effect during completion of construction. The applicant stated that at the initiation of fuel loading the top floor of the reactor building will be closed off.to all personnel except i
those involved'in the fuel loading operation.. Radiation control
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measures in_.accordance with the requirements cf 10 CFR 20 will bo in effect. During the fuel loading and completion-work in-other areas of the plant, the activity of all construction personnel will be. administrative 1y controlled.
Summa ry of those matters discussed, we believe that two require further clarification. These involve.the use of the' liquid radwaste system during fuel leading and low power test operation,' and substantiation for testing up to 5.MW(t) assuming unavailability. of secondary containment.
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R. C. DeYoung Tom Englehardt expressed his opinion that all items that will be i
incomplete in time for fuel loading and for reactor testing up to 5 MW(t) should be explicitly defined and discussed in detail, since these facts would have to be presented as testiinony to the AS6LB.
The applicant agreed and stated that this testimony would be available prior to the prehearing conference scheduled for April 7, 1970.
Domenic B. Vassallo, Project Leader PWR Projects Branch #1 Division of Reactor Licensing