ML19291B880

From kanterella
Jump to navigation Jump to search
Responds to Re Rescheduling of 791116 Meeting W/Util to Omaha,Ne,Rather than Silver Spring,Md.Due to Technical Nature of Meeting,Number of NRC Specialists Required.Next Meeting to Be Held 791211 in Omaha
ML19291B880
Person / Time
Site: Fort Calhoun 
Issue date: 11/29/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Kirschen A
CREIGHTON UNIV., OMAHA, NE
References
NUDOCS 7912140012
Download: ML19291B880 (1)


Text

oy(

'\\

  • o, UNITED STATES

'j NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D. C. 20555

/

November 29, 1979 Docket No. 50-285 Mr. Alan H. Kirshen Associate Professor of Law and Chairman, Natural Resources Committee, Citizens Advisory Board, Metropolitan Area Planning Agency Creighton University 2500 California Street Omaha, Nebraska 68178

Dear Mr. Kirshen:

By letter dated November 15, 1979 you requested that we reschedule our November 16, 1979 meeting with the Omaha Public Power District (OPPD) to an Omaha, Nebraska location rather than Silver Spring, Maryland.

As Mr. Gray of our legal staff discussed with you on November 15, the November 16th meeting was of a technical nature which involved the participation of a number of NRC specialists who are located in this

~ office.

We have, however, arranged to have our next meeting with OPPD in Omaha, Nebraska. As discussed with you, this meeting will be at 8:30 am on December 11, 1979 in the OPPD Engineering Office, Omaha, Nebraska.

Our meeting notice (Enclosure 1) is enclosed. A copy of the minutes of our November 16, 1979 meeting with OPPD is also enclosed (Enclosure 2).

Sincerely, h'Y.

p Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Enclosures:

1.

Meeting Notice 2.

Meeting Summary 1582 120 912140 O12

,1 -

Erd osure 1 l

',_.*'"h, j

'c, UNITED STATES f, b - [' i NUCLEAR REGULATORY COMMISSION i

j

-, e..d, r WASHINGTON, D. C. 20555

., >~ m. ;$g 8 1979 gm2 Docket No. 50-285 MEMORANDUM FOR: Robert W. Reid, Chief, Operating Reactors Branch #4, Division of Operating Reactors k

FROM:

Peter B. Erickson, Project Manager, Operating Reactors Branch #4, Division of Operating Reactors

SUBJECT:

FORTHCOMING MEETING WITH OMAHA PUBLIC POWER DISTRICT (OPPD)

TIME & DATE:

8:30 am, Tuesday I

December 11, 1979 LOCATION:

OPPD Engineering Office 4th Floor Conference Room 4th & Marcy Sts.

Omaha, Nebraska PURPOSE:

To discuss EXXON setpoint methodology to be used for Fort Calhoun, Cycle 6 Reload and Stretch Power PARTICIPANTS:

NRC P. Erickson, R. Label OPPD K. Morris, B. Hickel EXXON J. Owsley, et al S-W v

Peter B. Ericks6n, Project Manager Operating Reactors Branch $4 Division of Operating Reactors I"

1582 121 76e er f v

n

,9ngedas#

eu,

e. m.... -

,s

--<,e

/

\\

UNITED STATES

'(j NUCLEAR REGULATORY COMMISSION

.E W ASHINGTON. D. C. 20555

(

/

November 26, 1979 Docket No. 50-285 LICENSEE: Omaha Public Power District (OPPD) v FACILITY: Fort Calhoun

SUBJECT:

MINUTES OF NOVEMBER 16, 1979 MEETING TO DISCUSS FORT CALHOUN CYCLE 6 RELOAD AND, PROPOSED POWER INCREASE Subject meeting was held in Bethesda, Maryland. Those in attendance are

_ listed in Enclosure 1.

OPPD discussed the EXXON analysis of the Cycle 6 reload and the proposed increase in power from 1420 Megawatts thermal (Mwt) to 1500 Mwt. The OPPD schedule for submittal of a small break analysis was of significant interest because the analysis, as proposed, would be based on EXXON methods which have not been presented to the NRC.

Various options for submittal of the small break analysis were considered including the use of approved Combustion Engineering (CE) analysis and the

.results of TMI-2 studies. lists the options for F all break analysis.

In addition, OPPD was told that they must show that the small break analysis meets 10 CFR 50.46 and 10 CFR 50 Appendix K requirements.

The staff discussed the planned NRC audit of setpoint calculations for Cycle i

6 and NRC plans for a meeting with OPPD and EXXON to answer staff concerns about EXXON calculations of setpoints.

The proposed irradiation of one standard fuel assembly for a fourth cycle was also discussed.

P. B. Erickson, Project Manager Operating Reactors Branch #4 Division of Operating Reactors

Enclosures:

1 List of Attendees 2.

OPPD Sm. Break Options cc w/ enclosures:

See back of this pg.

1502 122 h ye y 79.t.2124$8f

},

_.m..._..

Enclosun i' m _

, y -

r y., p LIST OF ATTENDEES 11/16/79 OPPD MEETING S0-285

~<

b' NRC OPPD Peter B. Erickson Joseph Gasper

[

Richard Lobel Bruce J. Hickle Stephen Sands p

S. H. Weiss k

V. W. Panciera LeBOEUF, LAMB, LEIBY & MACRAE Harry H. Voigt Margaret R. A. Paradis EXXON NUCLEAR Gerald Owsley Jim ibrgan Thomas L. Krysinski PRICKARD, LOWE & GARRICK (OPPD)

Finn B. Skogen Thomas Robbins i

(OVER) h; F

F 1582 123 I

7 m

y e

OPPD SMALL BREAK OPTIONS (NRC VERSION)

NO STRETCH POWER STRETCH POWER l

i I

l CE Exxon CE Exxon Worst Small Redo Calculation Worst Break Is CE report applicable Break with According to Post with Drift to Cycle 6 with Exxon Dri ft Flux Model TMI Model at Higher Flux Model fuel ?

Post TMI Power Level Post TMI Deficiences Included Deficiencies '

Included i

-i Heference CE CE Report report and ex-Not Applicable plain why it is to Exxon Fuel.

f 4

Ln appl icable.

Redo Calculations s

i C7 with CE Methods, N

Incorporate Exxon

. J y ;'

Fuel.

p' 5'

3 N

1 p- (

.,L ng 89 o

1

..e r

l

-