ML20147J128

Requests Addl Info for Review of Reload for Cycle 2 Oper of Subj Facil.Requests Partial Responses to Questions as Info Is Dev,& Full Responses W/In 30 Days

ML20147J128
Person / Time
Site:	Browns Ferry
Issue date:	10/10/1978
From:	Ippolito T Office of Nuclear Reactor Regulation
To:	Niav Hughes TENNESSEE VALLEY AUTHORITY
References
NUDOCS 7810270239
Download: ML20147J128 (3)

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( f b, UP5tTED STATES (.

~t NUCLEAR REGULATORY COMMISslOM

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• o WAEHINGTON, D. C. 20555 4 9'  %

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OCTOBER 1 0 1978

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Docket No. 50-296 i

! Mr. N. B. Hughes Manager of Power Tennessee Valley Authority

830 Power Building

Chattanooga, Tennessee 37401 i

Dear Mr.' Hughes:

i Reference is made to your letter of August 3, 1978 (TVA-BFNP-TS-ll3) transmitting a reload analysis for cycle 2 operation of Browns Ferry Unit No. 3. To complete our review of the subject reload, we need the additional information identified in the enclosure. This request for additional information was informally transmitted to your staff by telecopier on September 22, 1978.

In view of projected startup date for Unit No. 3, we would appreciate partial responses to the enclosed questions as the information is developed. In any case, complete responses to all questions must be

. received, within 30 days of the date of this letter to meet your 1 proposed startup schedule.

Sincerely, I

I w 6Yopd Y f ThomasA.Oppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors l

i

Enclosure:

Request for Additional a Information 1

l cc w/ enclosures:

see next page 1

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Tennessee Valley Authority - -

( cc: H. S. Sanger, Jr., Esquire J General Counsel l' Tennessee Valley Aut&ority

400 Commerce Avenue .

E 118 33 C Knoxville, Tennessee 37902 ,

!. Mr. D. McCloud Tennessee Valley Authority  ; _ ,

303 Power Building - '

Chattanooga, Tennessee 37401 fir, Mr. William E. Garner Route 4, Box 354

.; Scottsboro, Alabama 34768 Mr. C. S. Walker Tennessee Valley Authority 400 Comerce Avenue W 9D199 C Knoxville, Tennessee 37902 Athens Public Library South and Forrest Athens, Alabama 35611 l

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c M BROWNS FERRY UNIT NO. 3 j REQUEST FOR ADDITIONAL INFORMATION k DOCKET NO. 50-296 i N \

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1. The transient analysA summarized in NED0-24128 have been performed k with the REDY code. A new improved code, ODYN, which is based on  ;,

f ,first principles, has been presented by GE. The staff review of ODYN di is expected to be completed within the next few months. In order to 7i assure the staff that the proposed change to the operating limit MCPR

.j- will not hold any unexpected development when the ODYN review is E . ,

completed, we request that the licensee supply an OD.YN licensing basis .

Y reanalysis of the transients. This should include an analysis of the p limiting pressure and power increase transient and thts feedwater p:: controller failure transient. Each of these transients with RFT lj, should be analysed with the proposed licensing basis ODYN code (as ll applied in the letter from E. D. Fuller (GE) to D. F. Ross (NRC), '

l] Impact of ODYU Transient Model on Plant Operating Limits, dated l]' June 26,1978). Further, in order to verify the margin in the REDY and ODYN licensing bases, a best estimate ODYN analysis (as applied in the above referenced letter) of the Limiting Pressure and Power Increase Transient with RPT should be presented.

2. The trip inputs for the recirculation pump trip following the Pressure

, and Power Increase transients originate in the turuine building which is non-seismically qualified. Therefore, provide an analysis of the consequences of the Limiting Pressure and Power Increase transient without taking credit for recirculation pump trip from these inputs and including the effect of turbine overspeed on recirculation flow, c (Alternatively, demonstrate the applicability of an analysis already f on file.) Provide peak vessel pressure, MCPR, fraction of rods in

! boiling transition, peak cladding temperature, maximum fuel average i

temperature, and maximum radiological consequences. T' 5 event is categorized as an accident and should meet the guide 10 of 10 CFR 4 Part 100. Provide all assumptions for the radiological consequen.:e j analysis.

3. The proposed technical specifications only specify func.tional testing .

f of the RPT initiating logic. Propose startup tests and surveillance requirements for verification of RPT delay times and flow coastdown j calculational assumptions. There should be a maximum and minimum i

specification of the delay tima and flow rate coastdown. Provide the results of the Limiting Power and Pressure Increase transient calculations with the minimum specification on delay time and the fast flow coastdown.

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