ML19254D398
| ML19254D398 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 10/12/1979 |
| From: | Nowicki S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910250442 | |
| Download: ML19254D398 (29) | |
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UNITED STATES
[] 3 f i NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 s
October 12, 1079
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Docket No. 50-10 LICENSEE: Commonwealth Edisen Company FACILITY: Dresden Station Unit No.1
SUBJECT:
Summary of September 20, 1979 Meeting Regarding Proposed Redesign of the Low Pressure Core Sprey NRC, Commonwealth Edison Company (CECO), and General Electric (GE) reoresentatives met in Rockville, Maryland, on September 20, 1979, to review the CECO proposed-redesign of the low pressure core spray for Dresden Unit No.1 (D-1).
The redesign was made to assure acceptable coolant spray rates in all fuel channels.
The meeting attendees are listed in Attachment 1.
Af ter a brief introduction by CECO, representatives from GE described various characteristics of the core spray design. The agenda and a copy of the view-graph presentation are provided in Attachment 2.
The significant issues discussed during the meeting are sumarized below:
1.
Schedule: Startup of D-1 is scheduled for August 1980.
Since the new core spray design will require fabrication of a new turning vane, installation of the replacement sparger and turning vane, and testing of the new spray distribution, the core spray is now the critical path item affecting D-1 startup.
2.
Purpose of Redesign: The redesign was made to resolve c'oncerns regarding the core spray pattern. The new design spray system will deliver an analyzed jet of water into each fuel channel.
3.
System Design: A new turning vane and spray piping will be fabricated to eliminate personnei exposure to radiation.
The redesign adds distribution piping to the existing sparger but does not affect the remainder of the existing core spray or turning vane systems. This should solve the core spray distri-bution question without raising new concerns related to modifi-cation of the existing structures.
The NRC staff did ask several questions relative to CECO derivation of the seismic input used in analyzing the seismic qualifications of the added distribution piping.
Some additional information will be required to complete our evaluation of the seismic analys1s.
1208 330 7910250 ~f)
- 4.
System Testing: The new distribution system will be hydraulically tested at the Vallecitos Laboratories prior to shipment to Drosden.
Messrs. Woods and Nowicki requested to be notified of the actual test schedule so that the staff could witness the tests.
5.
Requirements: CECO plans to periodically infonn the staff of the progress of the redesign program. The staff recommended that Ceco review the previously transmitted questions concerning the core spray system (old design) and respond to any unresolved concerns.
CECO agreed that it was appropriate to respond to the unresolved issues and committed to review the question list and prepare responses upon return to their corporate office.
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Stanley J. Nowicki, Project Manager Operating Reactors Branch #2 Division of Operating Reactors Attachments:
1.
List of Attendees 2.
Agenda /Viewgraphs cc w/attachnents:
See next page I
,/
. cc w/attachnents:
Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 "r. B. B. Stephenson Plant Superintendent Cresden Nuclear Pcwer Station Dural Route #1
crris, Illinois 60450 U. S. fluclear Regulatory Commission ATTN: Jimmy L. Barker P. O. Box 706 fforris, Illinois 60450 Susan N. Sekuler Assistant Attorney General Environnental Control. Division l i d 'n'. Re,ndol ph Street Saite 2315 Chicago, Illinois 60601 "crris Public Library EL; Liberty Street
-is, Illinois 60451 700RORGNL
LIST OF ATTENDEES SEPTEMBER 20, 1979
- CECt, C. Solbrig M. Turbak R. Janecek 9E_
K. Cook R. Fairfield R. Brugge R. Ernst D. Holland NRC C. Hofmayer T. Cheng A. Lee R. Woods S. Nowicki
MEETIflG AGEf10A DRESDEN-1 CORE SPRAY SYSTEM MODIFICATI0il SEPTEMBER 20, 1979 SUBJECT PRESEf1TER INTRODUCTION TURBAK PURPOSE OF MEETIllG BACKGR00 TID SYSTEM DESIGN OVERVIEW COOK THERMAL-HYDRAULICS ERNST T-H CRITERIA SYSTEf1PERFORFAtlCE TEST PROGRAi1 SYSTEM DESIGN HOLLAi!D MECHAilICAL ARRAtlGEMEllT DESIGti CRITERIA TECHillCAL
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ERNST DESIGil APID DEVELOPMEt!T SCHEDULE TURBAK
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AflD DISCUSSION TURBAK KWC:ena/581
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SYSTEM DESIGN OVERVIEW o
MAJOR DESIGN OBJECTIVES f11NIMIZE IMPACT ON EXISTING SYSTEM f11NIMIZE IMPACT ON TURNIflG VANE / SUPPORT DESIGt!
ELIMIflATE SPRAY DISTRIBUTION UNCEPTAINTIES o
NO SYSTEM CHANGES REQUIRED o
INJECTION SYSTEM ELIMINATES STEAM /DISTRIBUTIO!!
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FLOW CAPABILITIES SYSTEM CAPABILITY UNCHAtlGED BUNDLE FLOW ADE0VATE oo
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MECHAtlICAL DESIGN TURNING VANE / SUPPORT DESIGN UtlAFFECTED
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DESCRIPTION DIRECT INJECTION OF ECCS WATER INTO EACH BUNDLE NETWORK OF PIPES ALONG TURNING VANE GRID WATER SUPPLIED BY EXISTING PUMPS AND PIPING SINGLE JET PER BUNDLE RJE 9/20/79 G
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DEVELOPMENT PURPOSE A.
CONFIRM FLOW DISTRIBUTION B.
CONFIRM DETAILS OF JET GEOMETRY COMPLETE FULL SCALE HYDRAULIC MOCK-UP MOCK-UP OF GRID AND FUEL BUNDLES 2.
VERIFICATION FLOW TEST OF REACTOR HARDWARE (OR HYDRAULIC DUPLICATE) 800 - 2700 GPM MEASURE FLOW FROM EACH N0ZZLE RJE 9/20/79 1208 346
DRESDEN 1 CORE SPRAY MECHANICAL DESIGN MODIFIES EXISTING TURNING VANE /
CORE SPRAY DESIGN.
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CHANGES LIMITED TO INSIDE VESSEL.
NEW TURNING VANE / CORE SPRAY HEADER HARDWARE IS USED TO PRECLUDE RADIATION EXPOSURE DURING INSTALLATION.
DISTRIBUTION PIPES REPLACE THE CORE SPRAY N0ZZLES ON THE 6" CIRCULAR HEADER.
DISTRIBUTION PIPES RUN DOWN TO TURNING VANE GRID AND ACROSS GRID BETWEEN FUEL BUNDLES.
0.25 FLOW HOLE IN DISTRIBUTION PIPE FOR EACH BUNDLE.
SUPPORTS AT ENDS OF DISTRIBUTION PIPES CAPTURE BUT ALLOW FOR CONTRACTION.
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MECliANCIAL DESIGri CRITERIA EXISTING DESIGN 1.
STRUCTURAL INTEGRITY JUSTIFIED FOR SPARGER OPERATION -
INJECTION FLOW AND THERMAL CONTRACTION EFFECTS.
2.
FLOW INDUCED VISRATION (VORTEX SHEDDING), WITH NORMAL REACTOR OPERATION MEETS VELOCITY MARGli!,
3.
PRESSURE DROP MEETS SPARGER INTERNAL DESIGN PRESSURE.
DESIGN MODIFICATI0flS
-SAME AS 1, 2, AND 3 AB0VE 3.;
4.
A STATIC SEISMIC ANALYSIS WILL BE PERFORMED PATERIALS TURNING VANE WILL BE CONSTRUCTED FROM 405 S.S. AS WAS ORIGINAL DESIGN.
SPARGER PIPING WHICH WAS ORIGINALLY MADE OF 304 S.S. WILL BE MADE OF 316 S.S. WITH LOW CARBON.
DFH 9/17/79 1208 356
SUMMARY
HIGH CONFIDENCE /SHORT SCHEDULE UNIQUELY SUITED TO D-1 SIMPLE TEXTBOOK HYDRAULIC DESIGN DISTRIBUTION UNAFFECTED BY A.
HIGH PRESSURE ENVIRONMENT (140 PSIG)
B.
STEAM ATMOSPHERE UTILIZES EXISTING CORE SPRAY PUMPS AND P! PING UTILIZES EXISTING POST INCIDENT SYSTEM ADD GRID PIPING TO EXISTING TURNING VANE DESIGN FLOW VERIFICATION OF REACTOR HARDWARE RJE 9/20/79 1208 357
WEEKS 9/20 40 48 56 4
TURNING VANE FABRICATION l'
DESIGN M0CKUP GRID DEVICE i
PREPARE SPECIFICATIONS & DESIGN MODIFICATIONS TO TEST FACILITY PREPARE TEST SPECIFICATIONS FABRICATE TEST EQUIPMENT AND PREPARE TEST FACILITY TEST M0CKUP DEVICE FINAL GRID DESIGN - INPUT TO O
TURNING VANE FABRICATOR FABRICATE GRID JEVICE AND MOUNT ON TURNING VANE SilIP TURNING VANE TO VALLECITOS O
TEST FINAL GRID DEVICE CJ SillP llARDWARE N
S NRC UPDATE E]
O Cl G.
CO