ML20216J685

Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept

ML20216J685
Person / Time
Site:	Farley
Issue date:	03/16/1998
From:	SOUTHERN NUCLEAR OPERATING CO.
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ML20216J683	List: ML20216J678 ML20216J685
References
NUDOCS 9803240033
Download: ML20216J685 (4)

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, ATTACH. MENT H l

SNC Response to NRC Request For Additional Information Related to Power Uprate Submittal- Joseph M. Farley Nuclear Plant, Units 1 and 2 l

l CORRECTED PAGE NOS. 58 A 59 "FARLEY NUCLEAR PLANT UNITS 1 AND 2 POWER UPRATE PROJECT BOP LICENSINO REPORT" (A1TACHMENT 6 TO SNC SUBMITTAL DATED FEBRUARY 14,1997) i i

CORRECTED PAGE NO. 37 (TABLE E) l "FARLEY NUCLEAR PLANT RESPONSE TO REQUEST j FOR ADDITIONAL INFORMATION RELATED TO POWER UPRATE j FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS CHANGE l REQUEST" (ATTACHMENT I TO SNC SUBMFITAL DATED AUGUST 5,1997) 1 1

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, Case 1. An SGTR with a preaccident iodine spike of 30 pCi/ gm results in offsite doses less than 10 CFR 100 guidelines, which meets the acceptance criteria.

Thyroid Dose Whole Body Beta Skin (Rem) Dose (Rem) Dose (Rem)

EAB 19 0.15 0.20 LPZ, 7.7 0.06 0.07 Case 2. An SGTR with an accident initiated iodine spike with an appearance rate 500 times the equilibrium rate, corresponding to the technical specification limit of 0.5 pCi/gm results in offsite doses that are a small fraction (10%) of the 10 CFR 100 guidelines, which also meets the acceptance criteria.

I Thyroid Dose Whole Body' Beta Skin (Rem) Dose (Rem) Dose (Rem)

EAB 2.8 0.13 0.19 LPZ l.7 0.05 0.07 I

The potential for uncovery of the steam generator tubes during the event was also evaluated for uprated conditions. Assuming technical specification limit for RCS activity (0.5 Ci/gm) and leak rate (150 gpd to each intact generator) and release directly to the environment ( f.e., ac mixing with the secondary side water) for the first 30 minutes, the offsite doses remain a small fraction of the i 10 CFR 100 guidelines.

2.16.7.3.2 Evaluation of the Radiological Consequences of a Main Steam Line Break I'

The radiological consequences of the MSLB were evaluated utilizing the assumptions of Standard Rwiew Plan Section 15.1.5 and the RCS leak rates approved with Technical Specifications Amendments 132 (Unit 1) and 124 (Unit 2), f.e.,150 gpd/ intact steam generator mid 23.8 gpm from the ruptured steam generator. For the most limiting case (accident initiated iodine spike 500 times the normal iodine appearance rate and no secondary side mixing), the offsite doses are a ,

small fraction of the 10 CFR 100 guidelines which meet the acceptance criteria.

Thyroid Dose Whole Body Beta Skin (Rem) Dose (Rem) Dose (Rem)

EAB '? <1 <1 LPZ V, <1 i <1 i

BOP UPRATE LICENSING REPORT 58 FNP - UNITS 1 AND 2 03/16/98 l l

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In1kidstion, the impact ofimplementing steam generator tube altemate repair criteria on control I l room thyroid dose was evaluated for the most limiting accident initiated iodine spike case. For this case the control room thyroid dose was 2.3 Rem using the assumptions described above.

o 2.16.7.3.3 Evaluation of the Radiological Consequences of a Loss of Offsite Power, Loss of Load, Turbine Trip l

The radiological consequences of the bounding steam releases from a loss of offsite power, loss of load, and turbine trip were evaluated utilizing the asstimptions of Standard Review Plan Sections i

15.2.1-15.2-6, except that partition factors are assumed to be limited to 10.; f.e., there is no tube i uncovery nor immediate flashing of primary to secondary leakage consistent with the current FSAR, Section 15.2.9. These releases result in offsite doses which meet the acceptance criteria assuming no iodine spike.

Thyroid Dose Whole Body Beta Skin (Rem) Dose (Rem) Dose (Rem)

CAB 8.9 x 10'8 1.2 x 10 ' 7.9 x 10" LPZ 7.6 x 10' 8.1 x 10" 5.8 x 10" i

l A pre-existing spike which increases the RCS iodine concentrations to 30 Ci/gm DElm results )

in an increase in thyroid dose to 0.93 Rem and 0.82 Rem at the EAB and LPZ respectively.

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BOP UPRATE LICENSING REPORT 59 FNP - UNITS 1 AND 2 0386/98 l l o .

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TABLE E PARAMETERS USED IN STEAM LINE BREAK ANALYSES Core thermal power (MWt) 2831 Tube leak rate prior to accident 150 (gpd/per steam generator)

Tube leak rate after accident 150

-(gpd/per intact steam generator)

Tube leak rate after accident 23.8 j (gpm from ruptured steam generator)

Offsite power Lost Fuel defects (%) 1(*)

Secondary side DElm activity ( Ci/gm) 0.1 Iodine partition factor for initial steam 1.0 release from defective steam generator lodine partition factor in non-defective 0.1 l steam generators prior to and during ]

accident Time to isolate defective steam generator (h) 8 Initial steam release from defective steam 473,000 (0-30) generator (Ib) (min)

Steam release from two non-defective steam 339,000 (0-2) generators (Ib)(h) 730,000 (2-8)

Feedwater flow to two non-defective steam 442,000 (0-2) generators (Ib)(h) 791,000 (2-8)

Meteorology Accident (see FSAR Appendix 15b)

a. A pre-existing iodine spike of 9 pCi/gm or an accident initiated iodine spike 500 times the appearance rate for a normal prunary coolant DElm activity of 0.15 Ci/gm is assumed.

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