ML20090L697

Application for Amend to License DPR-22,changing Transient Analyses in FSAR

ML20090L697
Person / Time
Site:	Monticello
Issue date:	06/01/1973
From:	Larkin W NORTHERN STATES POWER CO.
To:
Shared Package
ML20090L685	List: ML20090L684 ML20090L697 ML20090L702
References
NUDOCS 9102120544
Download: ML20090L697 (5)

Text

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I L UNITED STATES ATO:!IC DiERGY C0bD11SSION r, '>

' NORTilERN STATES POWER COMPANY 4

Monticello Nucicar Generating Plant Docket No. 50-263 REQUEST FOR AUT!!ORIZATION OF A CHANGE IN TECHNICAL SPECIFICATIONS OF APPCIDIX A PROVISIONAL OPERATING LICENSE NO. DPR-22 (Change Request Dated June 1, 1973)

Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B. Exhibit A describes the proposed changes along with reasons for change. Exhibit B is a copy of the Technical Specifications marked up to indicate the proposed changes.

This request contains no restricted or other defense information. \

NORT11ERN STATES POWER COMPANY By L. >~

• Wade Larkin

,: + Group Vice President - Power Supply On this 2 day of- _//AL/ , 1973, before me a notary public in and for said County, personally appeared Wade Larkin, Group Vice President - Power Supply, and being first duly sworn acknowledged that he is authorized to execute this document in behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.

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[Jahn J Sayh f,( (,,/ Notary PuM'ic, llennepin County, Minnesota

Y JOHN J. SWTH w....y sc.. n.na..in coune,. mina..... l 4-l$; my comm;,,...i tipie.. Mae h 3. H76 f >

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!. EXHIBIT A f.

l MONTICELLO NUCLEAR GENERATING PIANT l ?" DOCKET NO. 50-263

, '4 l CHAIDE REQUEST DATED JUNE 1,1973

! , PROPOSED QIANGES TO THE TECHNICAL SPECIFICATI0IE j 'f APPENDIX A 0F PROVISIONAL OPERATING LICENSE NO. DPR-22 l

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Pursuant to 10 CFR 50 59 the holders of the above-mentioned license hereby l

.- propose the following changes to Appendix A,. Technical Specifications:

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I PROPOSED CHANGE 3

Section 2 3.F, Bases, change the following a  ?'

i - Line h, delete the words " .... ca shown in FSAR Figure 14 5 3 .... "

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i ' - Line 6, change the value "105%" to "110%"

- Line 7, change the value "1.9" to "1.8"

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Line 7, revice the last centence to read, " Reference FSAR Section y 14.5 1.2.2 and supplemental iWmation submitted February 13,

., 1973."

j y Section 2.2, Bases, change the fifth paragraph as follows:

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Lines 1 and 2, change the words " turbine trip" to " closure of all

,/ main steamline isolation valves" l

hm - Line 2," delete the words " .... with failure of the bypass systen p ....

g Line 4, change the value "1187" to "1183" l

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Line 4, change the words " turbine trip valve" to " main steamline

! ri isolation valve closure" l

9 Line 6, change the value "1293" to "1283"

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Section 2.4, Bases, change the second paragraph as follows:

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] - Line 5, change the words " turbine stop valve" to " main steamline isolation valve" 4

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p 53* \t Lines 6 through 9, change to read " . . . . closure while operating at

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W 1670 WT, followed by no main steamline isolation valve closure scrum but scram from an indirect (high flux) means. With the safety "

{g valves set as specified herein, the maximum vessel pressure (at the bottom of the pressure vessel) would be aboutl263 psig. See FSI.R h';A Section 4.4 3 and supplemental information submitted February 13,

, 1973 t' valuations presented indi . . . . "

N Section 31, Bases, change the eleventh paragraph (beginning on the

-' bottom of the second page) as fullows:

- Line 3, change "iput" to " input" n

1 - Lines 7 and 8, replace the centence "Ref Section 14 5 2.2 FSAR" With " Reference FSAR Section 14.5 1.2.2 and supplemental informa-

f. tion submitted February 13, 1973."

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,j Section 31 Bases, change the thirteenth paragraph (lower half of the third page) as follows:

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I - Line 4, add to the last sentence the words " .... and supplemental

.;r information submitted February 13, 1973."

Specification 3 3.C.1, chan6e the table to read as follows:

% Inserted From Ave Scram Insertion n Fully Withdrawn Times (Sec )

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• S 0 375 20 0 900 50 2.00 1 5 00 Specification 3 3.C.2, change the table to read as follows:

3 Percent of N

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Rod Inngth Inserted Seconds

], 5 0 398 4 20 0 954

[t 50 2.120 90 5 300 Y

Section 3 3.C and 4 3.C, Bases, change the first paragraph as follows: '

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i - Lines 8 and 9, replace the words " .... a turbine stop valve closure 9 with failure of the turbine bypass system . " with " . . . . closure a of the main steamline isolation valves with failure of tre valve clo-

, sure screm but an indirect scram from high flux."

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• 5Y ' - Line 11, change the value "1 9" to "1.8" h n

K - Line 12, change the value "390" to "290"  :

- Line 13, delete words beginning with "This is adequate .... " to

• the end of the paragraph. Beplace them with the words, "'Ihis is ig i,

adequate and conservative when compared with the typical time delay of about 210 mil 11se conda estimated from scram test results. Ap-F proximately the first 90 milliseconds of the time interval results

[ p,,~ from the sensor and circuit delays; at this point the pilot scram i solenoid deenergized. Approximately 120 milliseconds later control

1. F rod motion is estimated to begin. However, to be conservative,

@ control rod motion is not assumed to start until 200 milliseconds p'g' later. This value was included in the transient analyses and is included in the allowable scram insertion titnes of Specification 3 3. C 1 and 3 3. C.2. "

k*(,' Section 3 5.E, Bases, change as follows:

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D[ - Lines 8 through 11, delete the two sentences included within "All trancient analysic . . . . . . . . jeopardizing reactor safety. "

Specit'ication 3.6.E, change as follows:

4 , - Line 5, change the words "three safety / relief" to "four safety / relief" n

l," Section 3.6.E and h.6.E, Bases, change the third paragraph as follevs:

%r Line 2, replace the words " turbine trip initiated" with " main steam-bn line isolation valve closure" e -

Line 3, delete " . . . . no steam bypass system flow, ....

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Line 3, replace the words " .... turbine valve trip" with " main

& steamline isolation valve closure" Mg."~ .

- Line k, change the word " assured" to " assumed" g

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Line 5, chenge the value "35.4%" to "35%"

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Line 6, change the value "18. 5%" to "18%"

R - Line 6, change the words "three safety / relief" to "four safety / relief" y

, _ REASON FOR CHANGE f, On February 13, 1973 a letter from L 0 myer (NSP), to A Giambusso (USAEC)

entitled " Supplemental Report of a Change in the Transient Analysis as De-

.yP1 scribed in the FSAR" identified new assumptions used in nelyzing reactor i

power transients. The above proposed changes vill make the Technical Speci-f fications compatible with the results of that analysis.

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o EXHIBIT A o

4 PROPOSED Clyd3GE

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4- Section 2 3.D, lhces, chance the following

,- - Line 3 of paragraph 2, change "page 22" to "page 16"

-, Ceetion 2 3.H, Ihces, change the following:

. Line 2 of paragraph 2, change "page 22" to "psge 18" Section 3.1, Ibses, change the following1

- Line 1 of paragraph 13 (midd3a of race 39), change " valves are

- h 10%" to read " valves are :5;;10%. "

6 REASON F0h CIUdlGE 4'

Bece ctatemente vere p11nted incorrectly in the initial iscuance of Appendix  ;

A, Technical Spe cifications.

.q PROPOSED CHAN3E Section 3.6.E and 4.6.E, Bases, delete the second parn6raph statingt i"

"The operator vill cet the pressure settings at or below the cettings 1 listed. However, the actual set points can vary as listed in the f basis of Specification 2.4."

& REASON FOR CHMGE e

Tbic wording repeats the last two sentences of t'm previcus paragraph.

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