Text

Summary of 930429-30 Public Meeting W/Licensee in Boston,Ma to Review Results of Design Basis Accident Calculations in Chapter 15 of CE Sys 80+ Std Safety Analysis Rept.Attendees Listed in Encl 1
	ML20044F916
Person / Time
Site:	05200002
Issue date:	05/20/1993
From:	Essig T; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 9306010193
	Download: ML20044F916 (37)
	v • d • e

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[$

UNITED STATES 2

NUCLEAR REGULATORY COMMISSION re

/'f WASHINGTON, D.C. 205554X101

%,f w 8

May 20, 1993

0 Docket No.52-002 APPLICANT:

ABB-Combustion Engineering, Inc. (ABB-CE)

PROJECT:

CE System 80+

SUBJECT:

PUBLIC MEETING ON APRIL 29 AND 30, 1993, TO DISCUSS IMPLEMENTATION OF THE REVISED SOURCE TERM (NUREG-1465) FOR THE CE SYSTEM 80+

DESIGN A meeting was held on April 29 and 30,1993, at the Stone & Webster (S&W) offices in Boston, Massachusetts, between representatives of the U.S. Nuclear Regulatory Commission (NRC) and ABB-CE. The purpose of the meeting was to review the results of design basis accident calculations in Chapter 15 of the CE System 80+ standard safety analysis report (SSAR), as well as supporting computer models and definitions of inputs parameters for these models. provides a list of attendees.

As shown in the meeting agenda (Enclosure 2), the discussion of design basis accidents was separated into those considered likely to cause fuel damage and those which were not likely to cause such damage.

In all instances, CE representatives demonstrated that 10 CFR Part 100 dose reference values or relevant standard review plan acceptance criteria were met using the draft revised accident source term described in NUREG-1465.

The staff discussed the general approach utilized by ABB-CE in applying the NUREG-1465 accident source term guidance, as well as the bases for key assumptions and input parameter definitions.

Presentation materials used by ABB-CE are contained in Enclo-sure 3.

f The following commitments were made during the meeting:

1.

ABB-CE will provide a reference for the annulus building bypass value of 10 percent.

2.

ABB-CE will clarify the SSAR to indicate that no heavy loads will be permitted over areas containing spent fuel.

3.

ABB-CE will submit a revised SSAR Section 6.4 (control room habitability) i on or about May 14, 1993.

4.

ABB-CE will provide feedback to Nuclear Reactor Regulation Standardization Project Directorate regarding the resolution, if any, of the in-contain-ment, post-accident pH control issue which was scheduled to be discussed in the NRC/CE meeting in Charlotte, North Carolina, during the week of April 26, 1993.

Yh hI 9306010193 930520 PDR ADDCK 05200002 e

{,

A PDR

n. :

di - May 20, 1993 5.

After making certain editorial changes, ABB-CE will resubmit l

Tables 15.6.5-1 and 15.6.5-2 as Amendment N to the SSAR.

j 6.

ABB-CE will inform the NRC staff of conclusions which it feels may be l

drawn from its analyses of conformance of the System 80+ design with the United States Environmental Protection Agency's Protective Action Guide-lines for radiological emergencies.

7.

ABB-CE will provide its recommendations by May 17, 1993, to the NRC staff l

with regard to the use of the new accident source term, mission time, etc.

l in environmental qualification analyses for the System 80+ design.

1 8.

ABB-CE will discuss atmospheric dispersion factors appropriate to the control room air intake with Mr. J. Van Ramsdell of Battelle/ Pacific i

Northwest Laboratories.

9.

ABB-CE will submit revised exclusion area boundary and low population zone accident dose estimates for SSAR Chapter 15 along with the Section 6.4 submittal. ABB-CE representatives stated that this submittal would contain only minor revisions to the Chapter 15 doses.

10. NRC staff will consider specific credit which may be given to the approxi-mately 90' separation (relative to the point of release) of. the control

.l room ventilation system points of intake for the System 80+ design.

11. NRC staff will investigate options which may exist with regard to dissemi-nation of preliminary staff views on environmental qualification issues J

raised through application of the revised accident source term (NUREG-l 1465).

In addition to the above commitments, CE agreed with the staff's position that the details of a proposed orifice in the chemical and volume control system l

letdown line be included in an inspection test analysis, and acceptance i

criteria.

Dod$fitiSy l

i Thomas H. Essig,.^cting Section Chief Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal l

Office of Nuclear Reactor Regulation j

Enclosures:

As stated cc w/ enclosures:

j See next page DISTRIBUTION:

See next page OFC:

LA:PDST:ADAR (A)SC:PDST:ADAR NAME: PShea ()r' TEssig:sg 5f20f93 DATE: 05/0/93 05/w/93

)

0FFICIAL RECORD COPY:

DOCUMENT NAME: HIGSUM.CE

,J

l ABB-Combustion Engineering, Inc.

Docket No.52-002 i

cc:

Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing

)

ABB-Combustion Engineering, Inc.

l 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 I

Mr. C. B. Brinkman, Manager Washington Nuclear Operations l

ABB-Combustion Engineering, Inc.

~

12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 l

l Mr. Stan Ritterbusch Nuclear Systems Licensing t

ABB-Combustion Engineering, Inc.

1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 Mr. Sterling Franks i

U. S. Department of Energy NE-42 i

Washington, D.C.

205B5 j

Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Washington, D.C.

20503 i

Mr. Raymond Ng i

1776 Eye Street, N.W.

Suite 300 Washington, D.C.

20006 Joseph R. Egan, Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

1 Washington,-D.C. 20037-1128 Mr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.

1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 1

L d

DISTRIBUTION w/ enclosure:

Docket file ";,

'PDR~

PDST R/F DCrutchfield PShea TWambach MFranovich SMagruder RPerch, BH7 DJSTRIBUTI0ff w/o enclosures:

TMurley/fMiraglia, 12G18 RBcrchardt TEssig Jtee, 10D4 LSoffer, NLS324 KEccleston, 20024 JMoore, 15B18 ACRS (11)

GGrant, EDO 4

EJordan, 3701 l

GBagchi, 7H15 l

l 1

l

9 HEETING ATTENDEES l

APRIL 29 AND 30, 1993 I{NiE Oroanizational Affiliation Tom Essig NRC/NRR/PDST i

Jay Lee NRC/NRR/PRPB Len Soffer NRC/RES/SAIB Joe Baron S&W l

Keith Ferguson S&W

'i Sreela Ferguson S&W Zbig Jastrzebski ABB-CE Steve Stamm S&W R. Bradbury S&W Ken Eccleston NRC/NRR/PRPB 7

Stan Ritterbusch ABB-CE i

Jim Metcalf S&W Alex Kasprak S&W i

Glenn Stinson S&W Wu Peng S&W Steve McInall S&W l

I

\\

I i

-l

~ _ _

4

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{

a PROPOSED AGENDA ON SOURCE TERM i

Thursday, 4/29/93 - 8:30 AM, Conf Rs 2A i

Introduction - Jim Metcalf LOCA - S. Te*5usen, K. Terguson, J. Beren, R. Bradbury, J. Metcalf

Offsite i

e Control Room

1 Other Fuel Damage Accidents - Sreela Terguson, Joe Rezendes i

I Treatment of Costus/ Rubidium in Non-1hCA Tuol Darage Accidents - Uu Fang e

Innch e CEA Ejection - Uu Feng Offsite Control Room i

5

.)

Incked Rotor - Vu Feng e

e r

Offsite Control Room 5

e Fuel Handling Accident - Kelth Terguson Offette l

Control Room

Main Steamline Break - Clenn Etinson Offsite I

Control Room e Teedwater Line Break - Clenn Stinson e

t Offsite a

Control Room-i Non-Tuel Damage Accidents / Cffsit.e only - J. Rezendes

=

i

Locked Rotor (CIS)

I e - Mein Stesaline Sreak (FIS and Cis) f e Steam Cenerator Tube Rupture q

e 14tdown Line Break i

s Friday. 4/30/93 - 3:30 AM, Conf Rm 2A i

Fon-Tuel Demege Accidents / Control Room Only - 3. Terguson, C. Stinson i

Steam Generater Tube Rupture f

e i

e htdown Line Break i

l Onsite X/Qe - Sreela Terguson, Alex Kasprak, Jim Metcalf FAG Dose Calculation - K. Terguson, S. McInall, J. Metcalf, S. Ritterbusch t

Exit Comments NRC l

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.Zmplemen%knt Table $ Input Parameters for _ Control Room Dose - Steam Release Path Time SRR R2 X/O Y

CRI CRUt RC3 R3 R I (lffm)

(sec)

(Ib/sec)

'(1/sec)

(s/m'3)

(1/sec)

(m'3/s)

(m"3/s)

(1/sec)

( '/gec) 0 20 971.38 4.151E-05 1.22E-02 4.781 E-07 0

0.944 0

4.95E-04 2 Jog-]

100 971.38 4.151E-05 1.22E-02 7.171E-09 0.944 0.00472 1.888 1.48E-03 600 190.66 8.148E-06 1.22E-02 1.408E-09 0.944 0.00472 1.888 1.48E-03 1200

.110.13 4.700E-06 1.22E-02 8.130E-10 0.944 0.00472 1.088 1.48E-03 1220 97.58 4.170E-0G 1.22E-02 7.204E-10 0.944.

0.00472 1.888.

1.4BE-03 1800 97.58 4.170E-06 1.22E-02 7.204E-10 0.944 0.00472 1.888 1.48E-03 7200 143.6 6.137E-06 1.22E-02 1.060E-09 0.944 0.00472 1.888 1.48E-03 10332 42.58 1.820E-0G 1.22E-02 3.143E-10 0.944 0.00472 1.888 1.48E-03 28800--

42.58 1.820E-06 1.22E-02 3.1 A2E-10

.0.944 0.00472 1.888 1.48E-03 86400 0.944 0.00472 1.888 1.48E-03 345600 0.944 0.00472 1.888 1.48E-03 V

2592000 0.944 0.00472 1.888 1.48E-03 b

t

-g li CRSTDoL um N

e Tabic 5 Decay and Transfer Function, Steam Release Path - Control Room Rb-88 Decay lambda =

6.400E-04 (1/sec)

Time Lambda 1 Lambda 2 Lambda 3 E1 E2 E3 E12 E23 E13 E123 (soc)

(1/sec)

(1/ soc)

(-)

(sec)

(soc)

(sec*2) 0 6.492E-04 6.490E-04 6.490E-04 1.00E+00 1.00E+00 1.00E+00 20 6.492E-04 6.905E-04 1.144 E-03 987E-01 9.80E-01 9.77E-01 1.97E+01 1.96E+01 1.96E*01 1.97E+02 100 6.492E-04 6.905E-04 2.127E-03 9.49E-01 9.46E-01 8.44C-01 7.58 E+01 7.9 5E+01 7.18E+01 2.92E+03 600 6.442E-04 6.571E-04 2.127E43 7.23E-01 7.20E-01 3.45E-01 3 61E+02 2.55E+02 2.55C+02 7.16E+04 g

1200 6.492 E-04 6.537E-04 2.127E-03 0.77E-01 6.76E-01 2.79E-01 4.06E+02 2.69E*02 2.69E+02 926E+04 W

1220 6.492E-04 6.532E-04 2.127E-03 9.87E-01 9.87E-01 9.58E-01 1.97E+01 1.95E+01 1.95E+01 1.95E+02 1800 6.492E-04 6.532E-04 2.127E-03 6.86E41 685E-01 2.9 t E-01 3.98 E+02 2.67E+02 2.67E+02 8.84 E+04 og 7200

6. ' 92 E-04 6551E-04 2.127E-03 3.00E-02 2.91E-02 1.03E45 1.60E+02 1.97E+01 2.03E+01 9.46E+04 10332 6.492E-04 6.508 E-04 2.127E-03 1.31 E-01 1.30E-01 138E-03 4.09E+02 8.73E 41 8.77E+01 2.18E+05 28800 6.492E-04 6.508 E-04 2.127E-03 6.2tE-06 0.03E-06 8.65E-18 1.13E-01 4.08 E-03 420E-03 7.36E+01 86400 2.127E-03 6.06E-54 N

345000 2.127E-03 0.00 I

2592000 2.127E-03 0.00E+00 b

D Time E01 E02 E03 E012 E023 E0123 h

(sec)

(soc)

(sec)

(sec"2)

(sec'2)

(sec'3) o s

20 1.987E+01 1.986E+01 1.977E+01 1.982E+02 1.976E+02 1.3 87E+03 100 7.796E*01 7.783E+01 7.356E+01 3.088 E+03 2.970E+03 7.965E+04 600 4.270E+02 4.262E+02 3.078E+02 1.008 E+05 8.050E+04 1.376E+07 1200 4.969E+02 4.963E+02 3.389E+02 1.393E+05 1.068E+05 2.198E+07 1220 1.987E+01 1.987E+0!

1.958E+01 1.983E+02 1.963E+02 1.311 E+03 1800 4 833E+02 4.828E+02 3.332E+02 1.313E+05 1.015E+05 2.017E+07 7200 1.494 E+03 1.482 E+03 4.701E+02 2.037E+00 6.873E+05 0.130E+08 10332 1.339E+03 1.336E+03 4.695E+02 1.429E+06 5.871E+05 5.692E+08 28800 1.540E+03 1.537C+03 4.701E+02 2.306E+06 7.222E+05 1.112E+09 86400 4.701 E+02 345000 4.701E+02 2592000 4.701E+02

'b t g

Table G Control Room Integrated Concentration and inhalation intake, Steam Release Path (Rb-88)

R1=

2.30E-07 1/sec C R Vol =

1906 m*3 TOTAL TOTAL Time A1 A2 A3 INTEGCON1 INTEGCON2 INTEGCON3 INTEGCON INHALATN (sec)

(Ci)

(Cl-s/m*3) (Ci-s/m*3) (Cl-s/m'3) (Cl-s/m*3)

(C0 0

4.66E+ 05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 20 4.60E* 05 2.12E+00 1.01 E-05 3.54E-06 0.00E+00 0.00E+00 3.54E-08 1.23E-11 0

100 4.37E+05 1.00E+ 01 1.18E-05 3.17E-06 2.36E-08 3.89E-07 4.44E-07 1.54E-10 600 3.16E+05 4.34E+01 1.78E-05 1.02E-06 5.96E-07 1.91E-06 3.52E-06 1.22E-09 b

1200 2.14E+05 5.88E+01 1.99E-05 6.81E-07 1.98E-06 3.16E-06 5.82E-06 2.02E-09 tg 1220 2.11 E+05 5.90E+01 1.99E-05 2.44E-11 4.3GE-09 2.05E-07 2.09E-07 7.26E-11 1800 1.45E+05 5.97E+01 2.02E-05 3.70E-07 2.26E-06 3.48E-06 6.12E-06 2.12E-09 1

7200 4.35E+03 7.05E+ 00 4.59E-06 1.69E-05 2.28E-05 4.99E-06 4.47E-05 1.55E-08 q

10332 5.69E+02 1.33E+00 2.68E-07 9.39E-08 6.83E-07 1.13E-06 1.91E-06 6.62E-10 28800 3.53E-03 2.28E-05 4.73E-12 2.40E-08 1.58E-07 6.61E-08 2.48E-07 8.61 E-11 g

86400 0.00E+00 0.00E+ 00 2.87E-65 0.00E+00 0.00E+00 1.17E-12 1.17E-12 4.05E-16 345600 0.00E+00 0.00E+ 00 0.00E+00 7.07E-66 7.07E-66 2.45E-69 D

2592000 0.00E+00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 (f

I Summation 6.30E-05 2.19E-08 F.3 Summary Of Results TOTAL TOTAL ISOTOPE LAMBDA A10 INTEGCON INHALATN (1/sec)

(Ci)

(Cl-s/m*3)

(Ci)

~-

Rb-88 6.490E-04 4.66E+05 6.30E-05 2.19E-08 Rb-89 7.482E-04 6.02E+05 6.01E-05 2.09E-08 Cs-134 1.066E-08 4.83E+04 5.75E-04 1.99E-07 Cs-136 6.097E-07 1.87E+04 2.20E-04 7.64E-08 Cs-137 7.285E-1n 4.87E+ 04 5.80E-04 2.01E-07 f3 Cs-138 3.587E-04 1.05E+06 4.48E-04 1.55E-07 37 3

-Oh

7 Table Control Room Doso due to inhalation of Cs & Rb, Steam Release Path Control Room Inhalation Dose due to Cs and Rb (Rem)

Inhatation

- =-------------------------

Isotope Intake (Ci)

Gcnad Breast Lung R_ Marrow B Surface Thyroid Remainder Effective 9

Rb-88 2.19E-08 1.0GE-07 1.15E-07 1.19E-05 1.17E-07 1.19E-07 1.11 E-07 1.12E-06 1.83E-06 4

Rb-89 2.09E-08 1.03E-07 1.34E-07 5.25E-06 1.56E-07 1.96E-07 1.24E-07 6.29E-07 8.96E-07 Cs-134 1.99E-07 9.59E-03 7.97E-04 8.71 E-03 8.71E-03 8.12E-03 8.19E-03 1.03E-02 9.23E-03 g

Cs-136 7.64E-08 5.31E-04 4.72E-04 6.56E-04 5.26E-04 4.81 E-04 4.89E-04 6.19E-04 5.60E-04 t

Cs-137/Ba-137m 2.01 E-07 6.52E-03 5.83E-03 6.56E-03 6.18E-03 5.91 E-03 5.90E-03 6.79E-03 6.42E-03 Cs-138 1.55E-07 1.89E-06 2.31E-06 9.14E-04 2.27E-06 2.04E-06 2.05E-06 1.18E-05 1.58E-05 Total 1.06E-02 7.11 E-03 1.69E-02 1.54E-02 1.45E-02 1.46E-02 1.77E-02 1.62E-02 g

t:>

b

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w ex

N O3302 - UR - 005-/

RH TaNe Controt Room Dose due to immersion in the Airborne ActMty, Steam Release Path C R Equiv. Radius =

9.69 m Gamma Dose Beta Dose TotalIntegrated Isotope Concentration Conv. Fetr Gamma Dese Avg Energy Beta Dose (Cl-sec/m*3)

(Rem /hr per Ci/m*2)

(Rem)

(Mev per Dis)

(Rem)

Rb-58 6.30E-05 3.734 3.17E-07 2.07 3.00E-05 Rb-89 6.01 E-05 12.961 1.05E-06 1.015 1.40E-05 Cs-134 5.75E-04 11.437 8.85E-06 0.157 2.08E-05 Cs-136 2.20E-04 15.361 4.55E-06 0.1 5.06E-06 Cs-137/Ba-137m 5.80E-04 4.166 3.25E-06 0.232 3.09E-05 6

Cs-138 4.4SE-04 14.776 8.91E-06 1.220 1.26E-04 Total 2.69E-05 2.2SE-04 CR.5TSUI'l l

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.soto.cs

. CALCULATION SHEET 4

CALCULATION 3DENTIFICATION NUMBER

.g-E..

J.D.OR W.O.NO,

. DIVISION & GROUP CALCULATION NO.

OPTIONAL TASK CODE PAGE 24 of32 03308 un 002 - 2 N/A FIGURE 1 RELEASE PATHWAY MODEL LarTDoco Ltok *R e_aq m en S 20 anc 10 cfm 430 crys 2000efm 04008/8 X/0=

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STEAM GENERATORS 24 fus

STONE & WEBSTER ENGINEERING CORPORATION

.soto.cs CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER J.O.CR W.O.NO.

DIVISION & GROUP CALCULATION NO.

OPTIONAL TASK CODE PAGE 43 of 55 03308 UR 003 - 1 N/A FIGURE 1 SGTR w/o LOOP Primary Secondary side side DF=1 4000 cfm 5% Flash,166,239 lbm Reciro 0-30 min 10 cfm 2010 cfm 78,583 lbm

~

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4 STONE & WEBSTER ENGINEERING CORPORATION

.soto es CALCULATION SHEET CALCULATlON IDENTIFICATION NUMBER J.O.OR W.O.NO.

DIV s10N & GROUP CALCULATION NO.

OPTION AL TASK CODE PAGE 46 of 55 0330s UR 003-1 N/A FIGURE 2 SGTR w/ LOOP Primary Secondar) m side side DF=1

$g 4000cfm u 52,087 lbm is Rectre 1

5% Flash 0-30 min 10cfm 2010 cim

=

~

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.b o

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TABLE 2.3-2 3

ONSITE ACCIDENT y AT THE CONTROL R ~fQ SEC/M ) VALUES ORTH AIR INTAKE Release Point 0-8 Hour,

8-24 Hour 1-4 Day 4-30 Day Unit Vent - Top of 2.78E-3b 1.32I-3 2.54E-3 5.94E-4 Annulus Building I

Center Main Steam Valve 1.22E-2 (2)

(2)

House Number 1 1.2h \\

Center Main Steam Valve 3

(2)

House Number 2

[4,3c,g._

9.11E-4)

(2)

Edge Main Steam Valve House !; umber 1 Edge Main Steam Valve 1.5b}-3 (2)

(2)

House Number 2 4

Annulus Building Wall

[9.64E-4) 8.38E_4 f.73E-4)

@ 4)

6 O E-1 Iv'I t G ' R

'-3. to E -( - l-2 5 E-2.

f. W l.22 f

HDIES:

(1)

G E-3 = Z IB x 10-3 (2) Release period not greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(1) 14cn-LocA calcWeb syrp.3 a g#reo w n*n d i rctm 2lr IMrkc loci % 4.n L och Cakin:ent LOCA r

i (6

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. as e -3

t. o i e -3

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~.

N Amendment N April 1,

1993 I

l

CESSAR 8lMincums TABLE 2.3-3 3

ONSITE ACCIDENT r/Q (SEC/M ) h UES AT THE CONTROL ROOM SOUTH AIR INTAKE

__ Release Point 0-8 Hour 8-24 Hour 1-4 Day 4 30 Day s

my

' Unit Vent - Top of 2.64E-3 b Annulus Building 2.p2 s.

E-3

1. @E-3 3.87E-4 fo9 Center Main Steam Valve 9.90E-4 (2)

(2)

House Number 1 Center Main Steam Valve

1. 22 E-2 (2)

(2)

House Number 2 Edge Main Steam Valve 1.26E-3 (2)

(2)

House Number 1 Edge Main Steam Valve 9.11E-4)

(2)

House Number 2 4.E 6' -1 Annulus Building Wall 1.04E-3)

M

[4.45E-p EIE4)

C.69E-Q 3.b~E-Q

'R.9/E-Q 4 l E.-E.s

1. l R L !i kOTES:

(1)

GE Z~R x 10-3 (2)

Release period not greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(3) the,- LOCH C21cM;ws emf I a iron c e.cis& se conk I r1cm 2*r in4 & e toc 2% 4% LocA calm &S

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