ML20043B527

Summary of 900322 Meeting W/Bwr Owners Group Re Topical Rept NEDO-31400, Safety Evaluation for Eliminating BWR Main Steam Line Isolation Valve Closure Function & Scram Function of Main Steam Line Radiation Monitor. Supporting Info Encl

ML20043B527
Person / Time
Issue date:	04/23/1990
From:	Liza Cunningham Office of Nuclear Reactor Regulation
To:	Congel F Office of Nuclear Reactor Regulation
References
NUDOCS 9005300152
Download: ML20043B527 (8)

Text

P_.s

_l y 'yj s,'; r L ' L April 23.-1990

' MEMORANDUM FOR:

. Frank J. Congel, Director o

l Division of Radiation Protection

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and Emergency Preparedness

[

0ffice of. Nuclear Reactor Regulation FROM:-

LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection.

and Emergency Preparedness Office of Nuclear Reactor Regulation

SUMMARY

OF MEETING WITH BWR OWNERS GROUP ON TOPICAL.REFORT NED0-31400, " SAFETY EVALUATION FOR ELIMINATING THE BOILING WATER REACTOR MAIN STEAM

! ME ISOLATION VALVE CLOSURE FUNCTION AND SCRAM T CTION OF THE MAIN STEAM LINE RADIATION MONITOR"

.In response to a request from the BWR Owners Group (BWROG), PRPB staff members met with BWROG and General Electric representatives on March 22, 1990. The BWROG-working group is composed of' representatives from five utilities. The purpose of the meeting was to hear and discuss the BWROG responses to the staff's connents on the latest BWROG proposal and to attempt to resolve out-standing issues related to the staff review of the subject topical report.

A General Electric representative made the technical presentation, and with

.the ensuing discussion, general. agreement was reached that the BWROG had been responsive the'the NRC staff's questions. Copies of the.viewgraphs are enclosed.-

Further, we believe that the substantive technical issues have been resolved, and we received the BWROG's final written transmittal in early April 1990.

'After its receipt, we plan to have our draft Safety Evaluation Report completed by the end of June.

-/s/

LeMoine J. Cunningham, Chief Radiation Protection Branch ~

Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation

Enclosures:

List of Meeting Attendees Viewgraphs

Contact:

Janes E. Wigginton Distribution: LGreger, RIII WRussell, NRR LJCunningham, NRR Local PDRs JWiggington, NRR JMartin, NRR RCJones, NRR TCollins, NRR GThomas, NRR RBellamy, RI GYuhas, RV TEssig, NRR Centra'11FJles h PRPB Reading DCollins, RII FMiraglia, NRR BMurray, RIV RErickson, NRR RBarrett, NRR DOCUMENT NAME:

SUMMARY

MEETING Ml

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BWROG MEETING ATTENDEES I

March 22,1990 L

,NRC s

LeMoine J. Cunningham, PRPB.

Tom Essig...PRPB Jim Wiggington,.PRPB-Frank Skopec, PRPB

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3ames Martin, PRPB

. George Thomas. DST, SRXB

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o General Electric

-. Bill Zarbis-i

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l 2Jo'hn La Force s.

Illinois-Power (Clinton) 1

'T. B. Ellwood Boston Edison Company L

Jack Fulton.

'TVA (Bellefonte).

Joni N. Johnson.

Iowa Electrte (Duane Arnold)

-Norm Peterson-PSE&G (Hope Creek)

' John Hawrylak l(

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VIEWGRAPHS FOR-3/22/90 BWROG/NRC STAFI iEETING '

Oj ADDITIONAL MSLRM AUTOMATIC FUNCTIONS 7

o VARIES FROM PLANT TO PLANT 4

o MAY INCLUDE FOR EXAMPLE:

MAIN STEAM LINE DRAIN VALVES REACTOR WATER SAMPLE VALVES l

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1 TECHNICAL SPECIFICATIONS o

LIMITS AMOUNT OF I-131 IN REACTOR WATER TO A FRACTION OF THAT WHICH COULD BE INTRODUCED BY CRDA OR FLOW BLOCKAGE i

o TYPICALLY REQUIRE VESSEL ISOLATION IF VALUES EXCEED 4 MICR0 CURIES / GRAM o

CONTROLS AMOUNT OF NOBLE GAS INCREASE BASED ON RELEASE RATES o

NOT DIRECTLY CORRELATED TO STACK, ASSUMING A0G D/F, FOR 0FFSITE LIMITS i

0FFGAS TRENDS o

FOLLOWED BY EITHER:

0FFGAS PRE-TREATMENT MONITOR; AND/OR 0FFGAS POST-TREATMENT MONITOR o

PRE-TREATMENT SAMPLING / RAD MONITOR PREFERRED i

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o ISOLATION OF MAIN STEAM LINES

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o PREDICATED ON TECH SPEC FOR REACTOR WATER I-131 CONCENTRATION LIMITS AND TIMING o

NO GRADED RESPONSE, I.E., MULTIPLES OF 0FFGAS NOBLE GAS RELEASE RATES ARE NOT USED TO DIRECTLY PRECIPITATE VESSEL j

ISOLATION o

SCRAM WILL OCCUR ON APRM HIGH FLUX l

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j TECHNICAL BASIS FOR OFFGAS PRE-TREATMENT SETPOINT s:

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o ORIGINAL CONCERN ADDRESSED REDUCING AMOUNT OF ACTIVITY l

' ACCUMULATING IN OFFGAS SYSTEM i

o CURRENT SETPOINTS TYPICALLY REFLECT REDUCTION OF ACTIVITY TO TREATMENT SYSTEM AND INDIRECTLY MAINTENANCE OF 0FFSITE RELEASES L

4

4 0FFGAS POST-TREATMENT MONITOR o

o ACTS AS A MEASURE TO MAINTAIN OFFSITE DOSES ORIGINATING FROM 0FFGAS WITHIN SPECIFIED LIMITS

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NOT INTENDED TO SERVE AS A DE FACTO MEANS TO REDUCE M

l POTENTIAL CONTAMINATION / BUILDUP IN MAIN STEAM /0FFGAS SYSTEM 4

E.