ML20052F883

Forwards Franklin Research Ctr Request for Addl Info to Be Transmitted to Util Re PWR Main Steam Line Break W/ Continued Feedwater Addition

ML20052F883
Person / Time
Site:	Crystal River
Issue date:	04/21/1982
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Hancock J FLORIDA POWER CORP.
References
IEB-80-04, IEB-80-4, TAC-46831, NUDOCS 8205140084
Download: ML20052F883 (5)

Text

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a hh Qlh APRIL ~ ? 1 1902 DISTERf rTints (Docket Fi d fiRC PDR L PDR O

Docket flo. 50-an2 D sn OELD AE0D IE lir. J. A. Hancock ACRS-10 Vice President SMiner fluclear Operations RIngram Florida Power Corporation Gray File ATTil: Manager, floclear Licensing EBlackwood P. O. Box 14042; fl.A.C. H-2 H0rnstein St. Petersburg, Florida 33733

SUBJECT:

PWR HAlfi STEAM LIllE BREAK WITil C0llTI!!UED FEEDWATER ADDITIO!!

(IE BULLETIll 80-04) - REQUEST FOR ADDITIO!!AL IflF0PJ1ATIO!!

From our review of your responses to IE Bulletin 80-04 on Analysis of a PWR liain Steam Line Break With Continued Feedwater Addition for Crystal River Unit 3, we find we require additional information.

The information required is outlined in the enclosure. The infomation requirements were developed by our contractor Franklin Research Center. Please respond within 45 days of recefpt of this letter.

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

Sincerely, A m.hrojh N John F. Stolz, Chief Operating Reactors Branch #4 Divistorrof Licensing k

Enclosure:

Request for Additional

.i Infomation cc w/ enclosure:

See next page 8205140084 820421 PDR ADOCK 05000300 P

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OFFICI AL RECORD COPY umra no-ow.a r,nctcou m o

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50-302 Crystal River Unit No. 3 Florida Power Corporation cc w/ enclosure (s):

!!r. S. A. Brandimore Florida Power Corporation Mr. Robert B. Borsum

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Vice President and General Counsel Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Division i

St. Petersburg, Florida 33733 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20014 Mr. Wilbur Langely, Chairman i

Board of County Comissioners Mr. Tom Stetka. Resident Inspector Citrus County U.S. Nuclear Regulatory Commission Iverness, Florida 36250 Route #3. Box 717 Crystal River, Florida 32629 Regional Radiation Representative Mr. T. C. Lutkehaus Nuclear Plant Manager EPA Region IV Florida Power Corporation 345 Courtland Street, N.E.

Atlanta, Georgia 30308 P. O. Box 219 Crystal River, Florida 32629 i

1 Dureau of Intergovernmental Relations 660 Apalachee Parkway Crystal River Public Library Tallahassee, Florida 32304 4

668 N. W. First Avenue j

Crystal River, Florida 32629

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Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road i

Tallahassee, Florida 32301 o

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Attorney General Department of Legal Affairs 1

The Capitol Tallahassee, Florida 32304 I

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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Comission, Rcgion II 53 a ta, eor f

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REQUEST FOR ADDITIONAL INFORMATION ij l!

li PWR MAIN STEAM LINE BREAK WITH o

CONTINUED FEEDWATER ADDITION FLORIDA POWER CORPORATION l!

CRYSTAL RIVER UNIT 3

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,, NRC DOCKET NO. 50-302 FRC PROJECT C5508 NRC TAC NO. 46831 FRC ASSIGNMENT 5 i

t NRC CONTRACT NO. NRCQ41 130 FRCTASK 127

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Preparedby l

Franklin Research Center Author: F. Vosbury 20th and Race Street

,f Philadelphia, PA 19103 FRC Group Leader: R. C. Herrick Prepared for i

Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: P. Hearn April 5, 1982 I-

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0. Franklin Research Center A Division of The Franklin Institute The Ben wmn Franksn Pachey, Phde. Pt 19103(21S) 448 1000 e

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.1 Evaluation of the information contained in letters dated May 8, 1980 [1],

June 2, 1980 [2], September 3, 1981 (3], and November 17, 1981 [4] from Florida Power Corporation (FPC) to the Nuclear Regulatory Commission (NBC). relating to IE Bulletin 80-04, " Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition," revealed several items of concern. Additional information relating to these concerns is needed before a final evaluation can be made

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regarding the potential for exceeding containment design pressure or worsening of reactor return-to-power response.

This concern and the additional information needed to resolve this concern are identified in this Raquest for Additional Information.

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i CO M IE Bulletin 80-04 directs the Licensee to review the reactivity increase which results from a MSLB inside or outside the containment.

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In Reference 3, the analysis stated, 'No loss of offsite power was assumed." The analysis is not clear on whether this assumption was supported by a sensitivity study evaluating worst single failures.

REQUEST Please provide the following information concerning your analysis of reactivity response which results from a MSLB with continued feedwater l;

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addition:

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An evaluation to determine whether the reactor return to power is 1.

more sensitive for normal power availability or loss of offsite power.

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REFERENCES i

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1.

R. M. Bright (FPC)

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14tter to J. P. O' Reilly (NRC)

Subject:

Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition I

May 8, 1980 l

1 2.

P. Y. Barnard (FPC)

Letter to H. R. Denton (NBC)

Subjects Nuclear Safety Task Force Priority Items June 2, 1980 3.

F. Y. Barnard (FPC) l' Letter to J. F. 3tolz (NRC)

Subject:

Rupture Matrix Signals l

September 3, 1981 i

4.

W. A. Cross (FPC)

Letter to J. F. Stolz (NRC)

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Subject:

Rupture Matrix' Signals l

November 17, 1981 O

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O.- Res, ear _ch C.erter ranklin

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