Text

Proposed Tech Specs Re Application of Partial Drilled Model for Analyzing Retrofit Fuel Design Scheduled to Be Installed in Plant Reactor in Fall 1978 Refueling Outage
	ML20024G705
Person / Time
Site:	Monticello
Issue date:	03/21/1978
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20024G372	List: ML20024G371; ML20024G373; ML20024G705;
References
	NUDOCS 9104250417
	Download: ML20024G705 (8)
	v • d • e

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l EX111 BIT B LICENSE AMENDMENT REQUEST DATED MARCH 21, 1978 This exhibit consists of the fol.owing pages revised to incorporate all of the proposed Technical Specification changes:

vii 189H 1891 1891a (new page) 189J 189K 190 t

9104250417 780321 PDR ADDCK 05000263 p PDR

LIST OF FIGtlRIS Figure No. P a g e Pfo .

2.1-1 Deleted 2.3.1 APRM Flow Referenced Scram and Rod Block Trip Settings 2.3.2 Relationship Between Peak lleet Flur and Power for Pealing Factor of 3.08 12 4.1.1 'N' Factor - Graphical Aid in the Selection of an Adequate Interval itetween Tests 46 4.2.1 System Unavailability 74 1.4.1 Sodita Pent aborate Solution Voltme - Concent ration Requirements 92 3.4.2 Soditse Pentaborate Solution Temperature Requirements 93 3.6.1 Charge in Giarpy V Transition Temperature versus Neut ron Exposure 122 l 3.6.2 Minimum Teeperature versus Pressure for Pressure Tests 122A 3.6.3 Minimum Temperature versus Pressure for mchanical lleatup or Cooldown Following Nuclear Shutdown 1225 t

3.6.4 Mininta Temperature versus Pressure for Core Operation 122C 4.6.1 Deleted 4.6.2 Chloride St ress Corrosion Test Results 9 500*F 123 4.8.1 Sampling Locations - Radiation Enviroment al Monitoring Program 173 3.II.1-A Haximum Average 1.incar IIcat Generation Rat e versus Planar Average Exposure Monticello 8D219 Fuel 189tt

3. I I .1- B Haximum Average Linear lleat Generation Rate versus Planar Average Euposure m nticeIlo 8DR264 Fue1 I391 Maximum Average Linear lieat Generation Rate W rsus Planar Averane 18913 3.11.1-Ba Exposure, Monticello 8DR282 Fuel ytt REV

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5.0 DESIGN FEATURES 51 Gite A.

The reactor center line la located a t approximtely 8 0 810 f East as dotermined on the Minnecotst .- ,

eet North und 2,038,9?O feet approxima tely 1630 feet G 30 kT of theSta te Grid, G ath Zone. 'lhe neares t site boundary is defined by the minimum fenced area shown in FDAR Ficure 2 2 Uuo 2areactor center line and tir exclualun area is wind pattern, the (11rection of maxinun integrated dosage lino i

to the prevailing follows the northern boundary of the rich t-of-way for st ia. MM. Tt.e couthern proparty

5. ? Mactor Rsrlington Northern Railway.

l A.

The reactor c 're nhall ana l nt of n ,t m're th in ' % fuel a-t lim .

B.

The reactor enre rh tll shall ntain be b >ron carbi te t wier 121ceruciforn-ch (BhC) mpac ted itel e ntr il J u P . Tbc

+

control rod mterial 53 Reactor Vencel 7pprax i s tely 70' of theoretic:(1 density .

A.

The 575 F.pressure vessel shall be designed for a precoure of 160 p i c g and a temperature of on suction side of pump and 1248 prig at pump di:re ch't er 1148 rgeThepsig ccalant recirculatio recirculation system chall be desigt;ed in accor*lanc ' .

B.>th the precrure vessel and Vessel Codo Sections III and IX. with the ACME Boiler and Pressure 5.4 containment A.

The primary containment shall be of the prencur" absarption 134,200

,ch imber c: notru :tel of steel . The drym 11 rhall have au;Inving rrt ,ci natyr dryvell and an f t' and la designed to conrorn to Acm volune T

->il er an 1 l'r ccure Vercel of appr>ximately c,de section III Class B for an intern sl prmoure of 56 paig a t 281"E nnd un ext

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at 281 F. The abnorption chamber ch sll have a ermi pressure of psig total v,lume of approxim tely 176,250 ft3 .

5.0 190 REV h _ .. .. ..

.. --

ML20024G705

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