ML18029A297

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Requests Addl Info Re Cycle 2 Reload Submittal Dtd 840823. WCAP-10507 & cycle-specific Value of Power Margin of Demonstration Assembly Compared to Limiting Assembly Requested
ML18029A297
Person / Time
Site: Browns Ferry 
Issue date: 11/26/1984
From: Vassallo D
Office of Nuclear Reactor Regulation
To: Parris H
TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8412170404
Download: ML18029A297 (5)


Text

Docket No. 50-260 November 26, 1984 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanoo a

Tennessee 37401 g

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Dear Mr. Parris:

SUBJECT:

CYCLE 2 RELOAD - REQUEST FOR ADDITIONAL DOCUMENTATION -.

Re:

Browns Ferry Nuclear Plant, Unit 2 Me request the following information for use in connection with your Browns Ferry Unit 2 reload submittal dated August 23, 1984 (TS-199).

l.

You have referenced MCAP-10507 as a supporting document with respect to the demonstration assemblies.

However, this report has not been formally presented (docketed) for staff review.

In order that we may base Safety Evaluation conclusions on such a report it must be formally submitted and attested to.

Therefore please submit this document on your docket.

Since there is some confusion as to which version is correct, please submit either the correct version or the altered pages relative to the version dated March 1984 and marked "Preliminary Copy."

2.

Please provide the cycle specific value of the power margin of the demonstration assembly compared to the limiting assembly.

Also, please confirm that a linear relationship exists between bundle power and CPR.

Also, demonstrate that the margin conservatively accounts for nonconservative transient delta CPR and other nonconservatisms such as high void fraction in the channel for the demonstration assembly.

3.

Even though the values of the uncertainties in the various input parameters to the two different CPR correlations (i.e.,

GEXL and AA-74) are the same, the form of the correlations is different and may result in a different safety limit CPR for the two correlations.

Therefore either justify the use of a safety limit value of 1.07 for both assembly types or provide an estimation of the uncertainty in the assumption and show that sufficient margin exists to account for it.

4.

Revise your amendment request to incorporate QUAD + fuel assemblies into the Technical Specifications in a manner consistent with GE fuel (i.e., Sections 3.5 and 5.2).

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Mr. Hugh G. Parris This request for additional information is specific to one licensee.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Ori'ginal signe'd by/

Domenic B.i Vassallo, Chief Operating, Reactors Branch P2 Division of.Licens'ing cc:

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Hugh G. Parris Tennessee Valley Authority Browns Ferry Nuclear Plant, Units 1,

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CC:

H.

S. Sanger, Jr.,

Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 330 Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley'uthority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. Charles R. Christopher

Chairman, Limestone County Commission Post Office Box 188
Athens, Alabama 35611 Ira L. Meyers, M.D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Mr. H.

N. Culver 249A HBD 400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 James P. O'Reilly Regional Administrator Peoi.on II Office U.

S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 U.

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Environmental Protection Agency Region IV Office Regional Radiation Representative 345 Courtland Street, N.

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Atlanta, Georgia 30308 Resident Inspector U.

S. Nuclear Regulatory Commission Route 2, Box 311

Athens, Alabama 35611 Mr. Donald L. Williams, Jr.

Tennessee Valley Authority 400 West Summit Hill Drive, W10B85 Knoxville, Tennessee 37902 George

Jones, Manager, BFNP Tennessee Valley Authority Post Office Box 2000
Decatur, Alabama 35602 Mr. Oliver Havens U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 James A. Coffey Site Director, BFNP Tennessee Valley Authority Post Office Box 2000
Decatur, Alabama 35602