ML20055D974

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Discusses Reduction in Expected Consequences from Hardened Vent Mods to BWR Mark I Reactors.Estimates Based on Surrogate ATWS Sequences
ML20055D974
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/03/1990
From: Buslik A
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
NUDOCS 9007100215
Download: ML20055D974 (25)
v • d • e


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NOTE T0: File FROM: Arthur Buslik, PRAB/DSR/RES

SUBJECT:

REDUCTION IN EXPECTED. CONSEQUENCES FROM HARDENED VENT MODfFICATIONS TO BWR MARK I REACTORS Our, estimate of reduction in risk from the addition of hardened vents in BWR Mark I reactors depended-in part on consequence estimates for Peach Bottom, for sequences of the type averted by the addition of hardened vents.

'Thesa consequence estimates were based on surrogate anticipated-transient-without-scram sequences. The work was performed by Arthur Payne of Sandia National-Laboratories, and is documented in the enclosed telecopy from Arthur Payne to me, dated September 26, 1989.

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M 3 1990 NOTE 10: File FROM: Arthur Buslik, PRAB/DSR/RES

SUBJECT:

REDUCTION IN EXPECTED CONSEQUENCES FROM HARDENED VENT MODIFICATIONS TO BWR MARK 1 REACTORS Our estimate of reduction in risk from the addition of hardened vents in BWR Mark I reactors depended in part on consequence estimates for Peach Bottom, for sequences of the type averted by the addition of hardened vents.

These consequence estimates were based on surrogate anticipated-transient-without-scram sequences. The work was performed by Arthur Payne of Sandia National Laboratories, and is documented in the enclosed telecopy from Arthur Payne to me, dated September 26, 1989.

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, D- "'C CV AT'.'S with no S LC, go to low pre ssuro ad use ;ov pressure injection systems. .C ontainn.ent heata up . l 6 3- Vessel breach occurs' at low P.IV prussure and :here is no l injection. (i . e. . low pressure injection failed af':ar l containment failure). l l

i G- Containment Emils by wetwell renting befors core dam. ige starts. 3.elease is initia1L7 by SRV lines to SP and after vessel' broach by downcoaers to SP then to ree.euor building throu6h 18" vent lires.

E- Contaituent f: ails by drywell tupture eithor beforc core darnaga or during core damage bt..t befcre vess ul brs ach. ,

Initial release is by SRV lines to wetwell, back to

.drywell and out to- reactor building. After vesnel breach release is to drywell and out to. lib.

D- Containment f. alls by drywell lead ruptura sith. before core damage or during coro dama5e but before1 ve sual broach. Relaase is initially by SRV linet. to SP, back +

to drywe ll', - ' and then out tc refueling Elcor. /.ft:cr vessei bre act: release is to dryvell ane',' then out to  ;

refueling floor. '

i A- Containment fulls before vessel broach cc:ar5 A= No containment sprays are available.

O A- The core concesee interaction (C01' occurs alth no w:cr available.

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'aDure ' occurred before core damage stated. There r.r a two ways V

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'ha results are: .

nne 1: PD 50 mi - 4.15E 4/3.9E 8 - 1.6E+4 per-tieverts.

P3 1000 mL - 1.67E-3/3.9E-8 - 4.3E+4 per sieverts.

To:a1 cost - 124/3.9E.8 - 3.2E+9 DcIlirs.

nt.e 2: P3 50'mi - 3.00E-4/1.2E 6 - 6. .lE4 4 per sieverts. 1 PD 1000 mL - 2.00E 3/1.2E 8 - 1. 7E4 5 per sleverts. /

To:a1 Cost - 220/1.2E 8 - 1.9E+10 Dellire.

ni4 3: P3 50 mi - 7.62E-6/1.5E 10 - 5.0E+4 pe r sievert:s . I P3 1000 mL'- 2.96E 5/1.5E 10 - 1.9E+5 per sievert:s.

Total Cost - 3.39/1.5E 10 - 2.2E+10 Dc 11.s rc .

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