Text

Summary of 770622 Meeting W/Util,Nus Corp,Mpr Associates & GE-NED in Bethesda,Md Re Backup Core Spray Nozzle Tests. Agenda & Test Parameters Encl
	ML19345F120
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/11/1977
From:	Reeves E; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8102060750
	Download: ML19345F120 (40)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION s

3./_ Q WASHINGTON, D. C. 20555 Q'%~;if f

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JUL 111977 DOCKET No.: 50-155 LICENSEE:

CONSUMERS POWER COMPANY (CPCo)

FACILITY:

BIG ROCK POINT

SUBJECT:

SUMMARY

OF MEETING REGARDING BACK-UP CORE SPRAY N0ZZLE TESTS On June 22, 1977, representatives of CPCo met with representatives of the Nuclear Regulatory Comission (NRC) at Bethesda, Maryland. A listing of attendees is enclosed. The NRC staff requested the meeting to review recent test results for the Big Rock Point back-up core spray nozzle.

BACKGROUND During the review of the Big Rock Point Plant Emergency Core Cooling System (ECCS) an uncertainty was noted relating to the core spray nozzle sprey distribution. - A single failure in the ring spray line would require proper spray distribution from the back-up single cor'e spray nozzle. Thus, CPCo initiated a test program to determine the effect of steam pressure on the single core spray nozzle spray distribution.

Results of the tests conducted during May and June,1977 were presented by CFCo,

SUMMARY

After a short introduction by the NRC Project Manager, CPCo personnel and their consultants presented the test facility description and test results to date using vue-graphs and slides (copies attached as pages 1 through 36).

As a result of tests accomplished to date CPCo has determined that the existing back-up core spray nozzle will be replaced during the refueling outage startingin August,1977.

Approximately 300 tests have been run on the full scale model using the existing single spray nozzle and on a multiple nozzle replacement design.

Further tests are being accomplished at the Bartow Plant in Florida under the direction of CPCo. Tests to date indicate that the multiple design nozzle is feasible.

Additional testing will be done to prove the design.

8Io10607 76 L

The CPCo presentation was responsive to the staff's concerns and additional details were provided in the following areas:

1.

CPCo intentions to test the ring core spray soarger_

CPCo noted that this was a separate generic issue from the questions raised by the Commission Memorandum and Order of May 26, 1976.

(CPCo letter of January 19, 1977 advised the NRC of their plans to test the ring spray distribution at the conclusion of the back-up single nozzle spray tests.)

2.

Contractual arrangements for the Tests CPCo stated they have a contract with General Electric (GE) who has subcontracted to NUS Corporation.

MPR Associates are consultants to CPCo and CPCo is the owner of the pressure vessel, spray nozzle, etc.

The test. facility location is on an agreement basis with Florida Power Company.

3.

Comparison of test data with previou_ sly published data CPC0 has not compared the test data with published data due to the lack of much previously published data.- (On June 23, 1977 CPCo advised us that they had the report "NED0-20566-3, 77NED56 GE Analytical Model for LOCA in Accordance with 10 CFR 50 Appendix K, Amendment 3 Effect of Steam Envircnmen on BWR Core Spray Distribution" mentioned by a NRC staff member.

Since the report was.only recently received it had not been reviewed. -

4.

Basis for the minimum 1.0 gpm assembly flow rate CPCo indicated that the basis for the minimum assembly flow rate was included in their 1971 submittal and AEC staff approval of the back-up core spray system addition.

Yf Z

Edward A. Reeves, Project Manager Operating Reactors Branch #2 Division of Operating Reactors

Enclosure:

1.

List of Attendees 2.

CPCo Presentation Vue-Graphs & Slides

i.

CONSUMERS POWER COMPANY i

MEETING ATTENDANCE _

JUNE 22, 1977_

CPCo

NR_C, B. Beckius E. Reeves S. Chan M. Hodges.

D. Joos N. Anderson D. Bixel R. Frahm -

W. Skibisky L. Marsh R. Woods NUS Corp.

Z. Rosztoczy J. Shea G. Brown MPR Asso.

H. McCurdy l

GE-N r.D.

J. Alai K. Hess i

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AGENDA IVR MEETING WIT!! NRC PRESENTATION ON BIG ROCK CORE SPRAY TEST PROGRAM 1 p.m. June 22, 1977, Phillips Bldg.

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INTRODUCTION A.

Basis for No::le Tests B.

Big Rock Point Emergency Core Cooling System

~II.

TEST FACILITY DESCRIPTION A.

Physical Layout B.

Instrumentation C.

Flow Measurement Techniques III. TEST PARMETERS A.

Bounding Criteria 1.

Vessel Pressure Range 2.

Spray Flow Rates 3

Assembly Design Flow B.

Limiting Conditions IV. TEST PROGRAM A.

Conditions Established for Test B.

Test Procedures C.

Data Reduction V.

TEST RESULTS A.

Test Data on Present Big Rock No::le 1.

Parameters Affecting No::le ' Performance Condensation and Spray Subcooling a.

b.

Steam Flow and Distribution c.

Pressure 2.

Conc 1'usions Concerning Variables Affecting No: le Performance S.

Preliminary Test Data en ta Acceptable Replacer.ent Nozzle VI.

SUMARY ArrACHM&WrS :

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TEST OBJECT VE THE OBJEL'TVE OF THE TEST IS TO PROVE ACCEPTABLE SPRAY DISTRIBUTION IN A HIGH PRESStlRE, SATURATED STEAM A'IMOSFHERE, 4

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TEST PARAMETERS FOR THE BIG ROCK POINT i

BACKUP CORE SPRAY SYSTEM J

i A., BOUNDING CRITERIA i

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VESSEL PRESSURE RANGE 2.

SPRAY FLOW RATE RANGE j

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FUEL ASSEMBLY DESIGN FLOW

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- s CORE SPRAY SYSTEM CHARACTERISTICS USED IN TE BLOWDOWN ANALYSIS PERFORMED IN ACCOEDANCE WITH 10 CFR 50 APPENDIX K, AND SUBMITTED TO TE NRC ON ' JULY 25, 1975.

DATA FRCM THIS BLOWDOWN ANALYSIS FOPJ4S THE BASIS FCR ALL FRESENT }UEL EATUP ANALYSIS.

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BREAK WHICH REQUIRES RATED SFRAY AT THE HIGHEST REACTOR FRESSURE WHICH ALSO RESULTS IN THE HIGHEST PEAK CLAD TEMPERATURE LIMITING BREAK: 0.25 ft BREAK AT RECIRCULATI'CN SUCTION LINE.

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OF CORE SPRAY SYSTD/. CHARACTERISTICS IN THE BLOWDOWN ANALYSIS :

TIME OF REA7"oR-BREAK PCT RATED SPRAY PRESSURE

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DESIGN FLOW REQUIRDENT FOR ADEQUATE COOLING b

TE ENIMUM ALLOWABLE FLOW PER FUEL ASSDSLY IS 1.0 Gnd.

IN THE CASE OF THE LIMITING BREAK,1.0 GR4 PER ASSEGLY IS.

RE7JIRED AT A REACTOR PRESSURE OF 75 PSIG.

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TEMPERATURE (CEG F) 325 WATER FLOW (GPM)

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TEMPERATURE (DEG F) 83 N0Z2LE NO.

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TEMPERATURE (DEG F) 82 NoZ2LE NO.

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CONCLUSIONS ON VARIABLES AFFECTDIG BIG ROCK POINT N0ZZLE PERFORMANCE CONE CONTRACTION INCREASES WITH DiCREASED VESSEL PRESSURE (EITHER STEAM OR COMPRESSED AIR)

STEAM CONDENSATION DOES NOT APPEAR TO HAVE A SIGNIFICANT EFFECT SFRAY SUBC00 LING IS NOT AN IMPORTANT PARAMETER SFRAY DISTRIBUTION IS DEFENDENT ON THE LOCATION OF THE STEAM SOURCE (TOP ENTRY BEING THE MOST RESTRICTIVE) l 4

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f BIG ROCK POItaT CORE SPRAY TEST MULTIPLE N0ZZLE SPRAY TEST RUN NO.

SB46-1 OATE 6/18/77 PAGE 2 or 3 VESSEL PRESSURE (PSIG) 75 TEMPERATURE (CEG F) 323 WATER FLOW (GPu) 296 TEMPEGATURE (DEG F) 87 N0ZZLE NO.

1 MULTI (M)

VESSEL GRIO REPRESENTATION (GPM) 4.03 X

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2.00 X

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X 4.15 5.51 X

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2.37 X

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BIG ROCK PulNT CORE SPRAY TEST MULTIPLE N0ZZLE SPRAY TEST RUN NO.

SC46-1 DATE 6/18/77 PAGE 2 0F 3 VESSEL PRESSURE (PSIG) 75 TEMPERATURE (DEG F) 323 WATER FLOW-(GPM)

296, TEMPERATURE (OEG F) 86 NOZZLE NO.

1 MULTI (M)

VESSEL GRID REPRESENTATION (GPM) 4.94 X

X X

2.07 X

X X

X 2.16 3.61 X

X X

X 2.42 X

X X

1.62 X

X X

1.49 X

X X

1.43 1.94 X

X X

1.95 X

X 1.83 1.46 2.86 X

3.28 4.30 X

X X

2.80 3.29 2.08 1.89 e

X X

X 2.74 6.51 1.99 VESSEL GPMAVG-408.21 FoLLOWIM6 OffETR. @M 6 Para 6ER McDt Ct CKT40V

BIG ROCK POINT CORE SPRAY TEST MULTIPLE N0ZZLE SPRAY TEST RUN NO.

ST46-1 DATE 6/18/77 PAGE 2 0F 3 VESSEL PRESSURE (PSIG) 75, TEMPERATUPE (DEG F) 322 WATER FLOW (GPM)

296, TEMPERATURE (DEG F) 87 N0ZZLE NO.

1 MULTI (M)

VESSEL GRID REPRESENTATION (GPM) 3.50 X

X X

82 X

X X

X 2.69 3.66 X

X X

X 3.30 X

X X

2.81 X

X X

2.86 X

X X

2.11 2.76 X

X X

x X

2.24 X

X 3.14 2.16 2.73 X

2.73 3.24 X

X X

3.74 3.35 2.80 1.33 X

X X

1.99 3.44 3.30 VESSEL GPMAVG-389.05 3r l

FBLLbu)iO 6 UPPER STEM GPAR6Et McDiFLcA TicM

(

BIG ROCK AulNT CORE SPRAY TEST MULTIPLE N0ZZLE SPRAY TEST RUN NO.

S846-6 OATE 6/18/77 PAGE 2 0F 3 VESSEL PRESSURE (PSIG) 75 TEMPERATURE (nEG F) 323 WATER FLOW (GPM)

370, TEMPERATURE (DEG F) 87 t

N0ZZLE NO.

1 MULTI (M)

VESSEL GRID REPRESENTATION (GPM) 5.51 x

x X

X X

3.30 x

x X

X X

X 4.05 4.02 x

x x

x 2.76 x

x x

2.94 x

x x

x 2.71 x

x x

X 2.32 2.60 x

x x

2.91 x

X 3.32 2.17 3.12 x

2.60 4.42 x

x x

4.96 3.90 3.63 1.73 x

x x

3.07 4.15 4.19 VESSEL GPMAVG-482.18 s

t O

34

MEETING

SUMMARY

DISTRIBUTION

~

Docket NRC PDR Local PDR ORB #2 Reading i

NRR Reading _

B. C. Rusche E. G. Case V. Stello-K. R. Goller 4

D. Eisenhut T. J. Carter.

A. Schwencer G. Lear R. Reid W. Butler B. Grines R. Baer L. Shao Project Manager -

Attorney, OELD -

OI&E(3)

R. Diggs NRC Participants (Major)

R. Fraley, ACRS (16)

T. B. Abernathy, DTIE J. B. Buchanan Licensee

. -, -

ML19345F120

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