ML20024G162

From kanterella
Jump to navigation Jump to search
Requests Addl Info Re Review of Proposed Changes to Tech Specs to Decrease Main Steamline Low Pressure Setpoint & MCPR Operating Limit
ML20024G162
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 02/04/1976
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Mayer L
NORTHERN STATES POWER CO.
References
NUDOCS 9102070613
Download: ML20024G162 (3)


Text

--_

~

+4 x

/:

st.'

FEg 4 1976 DISTRIBUTION NRC PDR 1 !

/

Local PDR Docket ORB #2 Reading KRGoller

~/

Docket Nc. 50-263 TJCarter OElb OI4E.(3)

DEZiemann Northern states Power Company RSnaider AT!H: Mr. L. O. Mayer BBuckley Manager of Nuclear Support RMDiggs services DEisenhut 414 Nicollet Mall TRAbernathy Minneapolis, Minnesota 55401 JRBuchanan ACRS (16)

Centlemen:

Your letter of December 1,1975 requestal approval of proposed changes j

to Technical Specifications of the Provir.lonni Operating License for the Monticello Nuclear Generating Plant. The proposed changes involve

' decreasing the main steamline low pressure setpoint and the minimurs critical power ratio operating-limit. We are reviewing your suhnittal and have determined that the additional information describod in l

Enclosure A is necessary to continue our review.

To enable us to maintain our review schodule, please suhnit the requested information prior to February 27, 1976.

\\

Sincerely, M signed bF Dennis I. Ziemann Dennis L. Ziemann, Chief

[

Operating Reactors Branch f2 l

Division of Operating Reactors

Enclosure:

1 Request. for Additional Information l

cc w/cnclosure:

4 See next page i

/

e

,. s OR,:0RB #2 OR:

OR:0R_B_#2 _

o,....,

RS,naider:ro T

,_ ley _

DLZiemann._

.u.

2g /76 2/y76 2/A/76 on es,

form ABC 314 (Rev. 9 53) ABCM 0140 W u. s. novenmusut enentwo opricas eeva.sas nee 9102070613 760204 PDR ADOCK 05000263 P

PDR

l*'

O O

FEB 4 E76 Northern States Power Company I cc w/ enclosure:

t..

i Gerald.Charnoff, Esquire Shaw, Pittman, Potts 6 Trowbridge 910 - 17th Street, N. W.

Washington, D. C.

20006 1

?

Steve J. Gadler, P. E.

2120 Carter Avenue

'T',

j St. Paul, Minnesota 55108 u

l

,a 1-bandra S. Gardebring, Esquire n'.

i Counsel for Minnesots Pollution I.

Control Agency 1935 W. County Road B2 Roseville, Minnesota 55113 The Environmental Conservation Library j

1 Minneapolis Public Library 300 Nicollet I;all Minneapolis, Minnesota 55401 g

)

n l' '

I~l 7

r u

I s e-ees

~

5

=.. = :: = --- -

- - ~ ^^~^^ ~ ^-~ 2:=:^ X ^: ^

p 9

o l

NORTHERN STATES POWER COMPANY q

f FONTICELLO NUCLEAR GENERATINC Pg

)r p

DOCKET NO. 50-263 i

REQUEST FOR ADDITIONAL INFORMATION i

REVIEW OF PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS 10 DECREASE MAIN STEAMLINE LOW PRESSURE SE1TOINT AND MINIMUM CRITICAL POWER RATIO OPERATING LIMIT l

i We are reviewing the proposed changes to Technical Specifications which would i

decrease the main steamline low pressure setpoint and the minimum critical power ratio operating limit, and have identified questions related to these subj ects. The following information is requested:

i.

1.

For the spectrum of steamline breaks downstream of the main **

    • a"

-h

..me

=

steamline isolation valves (MSIV) provide the following:

(a)

An analysis of the change in the radiological consequences I

resulting from the reduction in the setpoint for MSIV closure on low steamline pressure from 850 psig to 825 psig.

So that we may perform an independent check, also provide the difference in the unt of steam and liquid released as a result of the lo r setpoint.

1 (b)

A discussion of the effects of the setpoint reduction on i"

peak cladding temperature and MCPR.

p 2.

.In the analysis of the failure of the turbine pressure regulator presented in your SAR, the main steamline isolation valves are assumed to start closing (initiating a reactor scram) when the low steamline pressure is' reached.

I, (a)

Identify other transients that assume MSIV closure and I,

reactor scram are initiated by the low steamline pressure signal.

(b)' Provide a reanalysis of the failure of the turbine pressure regulator transient, and the other transients identified in (a), assuming MSIV closure and reactor scram at the proposed setpoint of 825 psig.

6 3.

Were MCPR values of 1.38 and 1.29 for 8x8 and 7x7 fuel used as the initial thermal conditions for establishing the worst case for rod withdrawal error ? If so, what is the rod block setting f

and do the affected fuel bundles stay above a MCPR value of 1.06i

4.. Provide the scram reactivity c*r.ve for E0C5.

<l 2

._-.m,

-' ~~~-~" '""-"--~'~ * ""

~'" '