ML20113J022

Amend to Application for Ol,Changing Draft Tech Spec Figure 3.1.5-1 to Revise Ref Level in Standby Liquid Control Sys Storage Tank.Revised Figure Encl

ML20113J022
Person / Time
Site:	Fermi
Issue date:	01/22/1985
From:	Jens W DETROIT EDISON CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
NE-85-0052, NE-85-52, NUDOCS 8501250411
Download: ML20113J022 (3)

Text

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- ,- Wayne H. Jens

• .- Vea Preudent Nuclear Operations Ferrni4 6400 North Dmie Highway

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Newport Micnigan 48166

' ls (313) 5864150 January 22, 1985 NE-85-0052 Director of Nuclear Reactor Regulation Attention: Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Fermi 2 NRC Docket No. 50-341

Subject:

Technical Specification Change Request As a result of a recent revision to the reference level in the Standby Liquid Control System storage tank, it is necessary to revise Figure 3_.l.5-1 of the draft Fermi 2 Technical Specifications. A_ revised figure is attached.

In addition, a corresponding change to the Bases on page B 3/4 1-4 has been made as indicated in the attachment.

Please incorporate these changes in a revised draft and send a copy to Mr. O. K. Earle, Supervisor-Licensing.

Please direct any questions-'to Mr.-Earle at (313) 586-4211.

Sincerely, cc: (all with attachment)

Mr . P. M. Byron Mr. M. D. Lynch-

.USNRC,. Document Control Dask Washington, D.C. 20555 8501250411 PDRADOCKOh0 j 1 ,'

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• r -15 i I REGION OF APPROVED -

9 VOLUME -CONC E N T R ATION c

LEVEL HIGH LEVEL H > ,g ALARM (LOW ( / ALARM

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N 13.8

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g g.

$ -13.4 -OVE R FL OW N

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VOLUME g _

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-12.8 k

$ \ MINIMUM

- REQdlRED l $ CONC E NT RATION LINE g e -12 Q

U 4640 4880

-11 4500 4600 4700 4800 4900 5000 5100 5200 z

o l I I E V-NET TANK VOLUM E lG ALL ON S]

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SODIU M PENTABORATE VOL UME/ CONCENTRATION REQUIREMENTS FIGURE 3.1. 5 - 1

w REACTIVITY CONTROL SYSTEMS r3 - a , = ,  % , m.

BASES

"~ ~ " "

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM The standby liquid control system provides backup capability for bringing the reactor from full power to a cold, Xenon-free shutdown, assuming that this To meet the withdrawn control rods remain fixed in the rated power pattern.

objective it is necessary to infect a quantity of boron which produces a concen-tration of 660 ppe in the reactor core and other piping systems connected to To allow for potential leakage and improper mixing this the reactor vessel.

concentration is increased by 25%. The required concentration is achieved by _ g having a minimum available quantity of manons of sodium pentaborateThis quantity solution containing a minimum of 5500 lbs of sodium pentaborate.

of solution is a not amount which is above the pump suction, thus allowing for '

The pumping rate of 41.2 gpm provides a the portion which cannot be injected.

negative reactivity insertion rate over the permissible pentaborate solution volume range, which adequstely compensates for Thethe positive reactivity temperature requirementeffects is due to temperature and xenon during shutdown.

necessary to ensure that the sodium pentaborate remains in solution.

i With redundant pumps and explosive injection valves and with a highly reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inoperable or for longer l

periods of time with one of the redundant components inoperable.

l Surveillance requirements are established on a frequency that assures a Once the solution is established, boron con-high reliability of the system.

centration will not vary unless more boron or water is added, thus a check on the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution is available for use.

Replacement of the explos:.*e charges in the valves at regular intervals will assure that these valves v ll not fail because of deterioration of the i

charges.

1. C. J. Paone, R. C. Stirn and J. A. Woolley, " Rod Drop Accident Analysis for Large BWR's", G. E. Topical Report NEDO-10527, March 1972.

2.

C. J. Paone, R. C. Stirn and R. M. Young, Supplement 1 to NE00-10527, July 1972.

3. J. M. Haun, C. J. Paone and R. C. Stirn, Addendum 2, " Exposed Cores",

Supplement 2 to NEDO-10527, January 1973.

FERMI - UNIT 2 8 3/4 1-4 1

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