ML20042E230

From kanterella
Jump to navigation Jump to search
Summary of 900315 Meeting to Discuss Differences in Radiological Assumptions Used in Reviewing BWR Owners Group & Advanced BWR Safety Analyses Re Generic Issue C-8
ML20042E230
Person / Time
Issue date: 03/26/1990
From: Trottier E
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
REF-GTECI-C-08, REF-GTECI-OS, TASK-C-08, TASK-C-8, TASK-OR NUDOCS 9004200462
Download: ML20042E230 (7)


Text

4 M

. @ ElO e

[

w '\\

UNITED STATES

\\

NUCLEAR REGULATORY COMMISSION e

i 5

.I usmwoTow. o. c. rosss

/

March 26, 1990 (t....

MEETING StMMARY

SUBJECT:

INTERNAL MEETING ON RA010 LOGICAL ASSUMPTIONS TO BE USED IN REVIEWING BWROG AND ABWR SAFETY AMLYS!S ASC0CIATED WITH GENERIC ISSUE C-8 DATE:

March 15,1990-TIME:

08:05 - 09:45 LOCATION: One White Flint North 6 B 11 PURPOSE: Resolve differences in radiological assumptions being used by various NRC groups reviewing BWR submittels.

===1.

Background===

Thitmeetingwascalledasaresultofconfusion(realorperceived)in comunication between NPC and GE regarding various criteria to be used during the review of BWROG and ABWR submittals. Both GE and the NRC have contributed to this confusion; GE through their dearth of "on-the-docket" technical positions, arf the NRC through a fractured review process sometimes lacking coordination.

11. Hecting Highlights The meeting began with a very brief sumary of previous meetings and significant events since 7 December 1989, the date of the initial meeting with the BWROG on G.I. C-8 and elimination of the LCS. The floor was then opened to an unstructured and free-rarging discussion of past policies and decisions that have brought us to this point, as well as possible positions and recommendations that might yield technically sound re?ults.

The following significant points were made during the discussion:

1.

The ABWR SAR does not include an LCS.

2.

The ABWR SAR assumes seismically intact MSLs and main condenser to meet part 100 limits. The GE ABWR group has stated, however, that they plan to meet the radiological criteria of Part 100 without credit for seismically intact MSLs and main condenser.

3.

If the GE ABWR group plans to apply for a Part 100 exemption, NRC manage-ment (i.e.,Dr.Murley)isnotawareofsuchplans.

4.

Is containment spray safety related? (AreviewofarecentlylicensedBWR with Mk 11 containment shows containment spray headers seismically cualified

[

Category 1, constructed to Class C, but upgraded to Class B by volumetric

  1. ps 9oo42co4sa 90o326

~

OFM qy4 y[J PDR TOPHP ENVGENE NRC FE CENTER COPY c

e e

2 exam of all circumferential welds, and isolation valves Q listed, seismic Catepory I and safety Class A or B.) Containment spray at this plant is constructed and tested to meet setrmic Category I and appropriate safety related requirements.

5.

There are three conditions that must be satisfied for the BWROG to take credit for seismically intact Mst.s and main condenser:

a technicall sound presentation documenting functionality (pressure retention)yafter a seismic event, a revision to the current NRC definition of functionality, ar.d a technically sound model for ledine mixing and plateout in the main steam lines and main condenser.

6.

Exemptions granted to current generation BWRs would be granted to ABWRs, absent design differences that affect the requested exemption.

A memorandum of discussion points for this meeting was prepared and distributed by Frank Congel. These discussion points are included here as Problems and Possible Solutions, and Potential Part 100 Dose Reduction Assumptions.

ThertetingconcludedwithagreementthhtThadani(DST)andCongel(DREP)would meet the week of 19 March to consider the discussion points (and perhaps others) or which the staff is willing to negotiate. The intended result would be te establitb acceptable staff positions for use in reviews of SAR Chapter 15, Accident Analysis.

Meeting ecVourned at 09:45 FUTlTE MEETINGS May, 1990- Review and discuss BWROG draft final report on seismic aspects and functionality of main steam piping and main condenser; working level meeting on ric'iological aspects (tentative and in series ith~seismicmeeting).

Ed Trottier, Project Manager i

Project Directorate 1-2 j

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Enclosures:

i 1.

CVROG/ABWR Radiological Problems and Possible Solutions 2.

DWROG/ABWR Potential Part 100 Dose Reduction Assumptions 3.

Attendance List 1

I t

l 1

O 4

I s

Y$"R"BUT10N,,

.,723mmIM:lM::.]

NRC PDR l.ocal PDR 3

JSnierek -

i PDI-2 Reeding WButler ETrottier OGC EJordan, MNBB 3701-CShiraki i

CMcCracken tCunningham WTravers RAnand i

FWitt JLee CNichols JMartin WButler DScaletti TEssig JKudrick CMiller CGraves AThadani FCongel ACRS(10)

JDyer, MS 17021 i

4 t

i s

t i

h'

~

(Gact.wn L A.

PROBLEMS e

J.

GE STATES VERBALLY THAT IT WILL NOT REQUEST AN EXEMPTION TO PART 100 FOR THE ABWR.

2. CURRENT ABWR SAR INCLUDES CREDITS FOR MSL AND dONDENSER.

WITH THESE CREDITS,' DOSES ARE WELL BELOW PART 100 LIMITS.

3.

GE INTENDS TO REVISE 1TS SAR TO CONSIDER ONLY SAFETY

[

GRADE SYSTEMS IN ITS PART 100 DOSE ESTIMATES. GE WILL HAVE TO BE INNOVATIVE TO PASS THE PART 100 DOSE ~ TEST 5.

EXCEPTIONS TO SOME S1AFF POSITIONS MAY BE NECESSARY.

4 WITHOUT LCS, AND WITHOUT THE.MSL AND CONDENSER, AND USING i

DNLY HISTORICALLY APPLIED STAFF DOSE MODELING, ABWR PART 100 DOSES WERE ESTIMATED BY THE STAFF TO BE FAR IN EXCESS OF PART 100 LIMIT OF 300 REM THYRO!D FOR A REASONABLY SIZED SITE.

e B. POSSIBLE SOLUTIONS 1.

GE REQUESTS AN EXEMPTION FROM PART 100 TO ACCREDIT NON-SEISMICALLY GUALIFIED MSLs AND CONDENSER.

QE

2. NRC STAFF CONCLUDES THAT MSLs AND CONDENSER ARE QUALIFIED TO SUFFICIENT EXTENT FOR THE ABWR SSE AND ACCEPTABLE SITE DIMENSIONS.

o QE 3.

NOT REQUIRE A LCS AND GIVE NO CREDIT FOR NON-SEISMICALLY OUALIFJED SYSTEMS. IN THIS INSTANCE, PREVIOUSLY UNAPPLIED CREDITS FOR BASIC PHYSICS AND CHEMISTRY AND PHENOMENOLOGY IN SAFETY GRADE SYSTEMS WOULD NEED TO BE ALLOWED FOR PART 100 TO STILL BE MET.

A LIST OF POTENTIAL, PREVIOUSLY UNAPPLIED DOSE REDUCTION CREDITS FOR SIESMICALLY QUALIFIED SYSTEMS IS ATTACHED. SOME OF THESE ARE NOT ALLOWED BY CURRENT SRP AND/ OR REG. GUIDE STATEMENTS.

QE 4

REQUIRE LCSs IN ALL BWRs (ABWR AND OLD BWRs) l

Endowse 1

==

1 POTENTIAL ESF GRADE SYSTEM DOSE REDUCTION PARAMETERS YET TO BE APPLIED EXPLICITLY IN PART 100 DOSE CALCULATIONS COGNIZANT OFFICE /DIV r

Efd TOPIC E

COMMENT /

CAVEAT o CHEM. FORM I 1 TO 1/10 ORNL CON-TRACT o DELAY IN T!D 1 TO 1/10 2ERO TIME UNCERTAIN.

BNL CON-TRACT.

o MAGNITUDE OF UNCERTAIN DECREASE TID RELEASE UNNECESSARY NRR/DREP o GROUND DEPOSITION 1/2 TO 1/7 FORBIDDEN BY R.G.1'3 o WIND MEANDER 1/2 TO 1/3 INCLUDED IN ALL MODERN CODES o FINITE CLOUD WB 1/2 TO 1/5 DITTO DOSE MODEL l

o ICRP 30 1/2 FOR THY DITTO o DEPOSITION IN 1/2 TO 1/10 LARGE AREA S.G. MSL TUNNEL AVAILABLE o HOLDUP IN S.G.

1/2 TO 1/5 DEPENDS ON MSL TUNNEL AT EAB DEF'N OF 2ERO TIME o DEPOSITION IN 1/5 TO 1/20 HOURS DELAY REACTOR BLDG.

ALSO I

o HOLDUP IN 1/3 TO 1/4 7 OF S MSIVs 3 MSLs AT EAB.

CLOSE AT T=

1 AT LP2.

"ZERO" o EMERGENCY 1 TO 1/60 NOT EXCLUD-

RESPONSE

AT LPZ ED HIGHLY CONTENTIOUS l

.-r

~*

NC S QIl(f L.

i

_=

1 t

NRR/DET TOPIC

+

QxEu COMMENT o DELAY IN T!D UNCERTAIN N.G. DECAY NO I DECAY l

o HPCS 1 TO 1/10 BLACKOUT RECOVERY 7 o STEAM /L!DUID 1/10 TO 1/50 CONTA!N PARTITIONING FOR ! (DELAY-CODE AND IN DRYWELL ED T!D)

NUREG-CR-4949 o CONT. PRESS.

1/2 TO 1/10 LEAKAGE VS TIME VS T!ME i

NRR/ DST o SUPP. POOL ORG. 1 (4*/.)

BYPASS FRAC.

UNSCRUBBED.

AND SCRUB.

1 TO 1/100 o DRYWELL SPRAYS 1 TO 1/20 G.E. DOES (S.G. IN ABWR)

NOT WANT CREDITS o WETWELL SPRAYS 1 TO 1/20 lbid.

(S.G. IN ABWR) o MSIV LEAK 1 TO 1/10 OYST. CRK.

RATE VS TIME PRECIDENT o CONT. LEAK 1 TO 1/10 OYST. CRK.

RATE VS PRESS.

PRECIDENT l

l

/

7 4

/h. - @.... --._.O../h) C d'.

[W

..---...~..F.'-.T..--------.-._---__.

53 U

.L. s..e.. k. f

. /r i

r l

A M n-c

_.D ' W;%biw C LYDE" SNIEA&/

fb.,[-2 l

Ccv.049 /??ecMcC4J

.J'i'L-8 t

/ c&WWIVG//h/11 fSP8

../.) D 1 RPrMJ\\ 6 09P RPtJ A 6 to.t S P L B._.

FMN4

3. W !T r..

P tC 6.

T

.-e.w..w

,e.-

m

....e. e.o e-w w...

  • .=.ae.e deg~~e C k ArIM (2. A/t t.lt o/J_. __._ ___ RL.h_ _

GM k8 M3. _._..

lui f furtcK.

Pb 1-7--

b u l k _. _. _ _.._.. P a s t 4

m To us LRs ( 6 filf 6 s

e P

')

.) y k e.# *y*

8 h

4

- t.,. c.

(I),!\\04 - -.._....

8n 0

$ V$

.se oK Tiinw I.. -

/Y M T

me W.ph esD.

eda. ^ -

  • =4

&W a.-.e.e.

.Wo4ee h e G6 D'. g.4.se im. e

.s, es..q..te m9st' es.she m

5.

u

... e

...--...,.....wo....

~

l w