ML20004E019
| ML20004E019 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/04/1981 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8106100600 | |
| Download: ML20004E019 (30) | |
Text
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7
- ( ***20k' UNITED STATES 9
['
'g NUCLEAR REGULATORY COMMISSION
- E W ASHINGTON, D. C. 20555 o
M4 El Docket No. 50-341 APPLICANT:
DETROIT EDISON COMPANY FACILITY:
Fermi 2
SUBJECT:
SU!EARY OF MAY 20, 1981 OL REVIEW MEETING REGARDING MARK I CONTAINMENT STRUCTURAL ANALYSIS The purpose of the meeting was to discuss applicant's interim evaluation of the modified design of the Fermi 2 containment and associated piping systems.
Applicant's representatives were L. Schuerman, D. Lehnert, A.
Higgnbotham (Nutech) and N. Edwards. NRC staff present were C. P. Tan, P. T. Kuo, D. Terao, and L. Kintner. A copy of the slides used in the meeting is enclosed.
The applicant had submitted an interim Plant Unique Analysis (PUA) that did not consider the condensation oscillation load prior to the issuance of staff's load definition report (NUREG-0661). The current calculations as presented in the meeting include the condensation oscillation load and its effects on the containment.
A mitered joint saddle structure has been added to the torus to accommodate the condensation oscillation load. The saddle structure is welded to the torus and bolted to the basemat.
(See page 10 of Enclosure)
The staff requested that the results of the current interim PUA analysis as presented in the meeting be submitted by the end of May 1981, including a comparison of loads and criteria with those in NUREG-0661. Staff also requested that a fatigue analysis of safety / relief valve discharge piping in the air space of the wet well be made.
The staff stated that the final Plant Unique Analysis would be reviewed by the same staff groups that will review operating BWRs.
However the schedule must be compatible with the licensing schedule. Therefore staff requested 810610hD
.o 2
that the Plant unique Analysis be submitted prior to March 1,1982 to allow time for review prior to issuing the operating license.
Subsequent to this meeting and a meeting with the BWR Mark I Owners Group, staff recognized that the analysis of attached piping must be done after the torus analysis is completed and changed the requested submittal date to May 1,1982.
l Lv L. L. Kintner, Project Manager Licensing Branch No.1 Division of Licensing
Enclosure:
As stated cc:
See next page
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Mr. Harry Tauber Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc: Eugene B. Thomas, Jr., Esq.
David E. Howell, Esq.
LeBoeuf, Lamb, Leiby & MacRae 21916 John R 1333 New Hampshire Avenue, N. W.
Hazel Park, Michigan 48030 Washington, D. C.
20036 Mr. Bruce Little Peter A. Marquardt, Esq.
IJ. S. Nuclear Regulatory Commission Co-Counsel Resident Inspector's Office Thh Detroit Edison Company 6450 W. Dixie Highway 2000 Second Avenue Newport, Michigan 48166 Detroit, Michigan 48226 Dr. Wayne Jens Mr. William J. Fahrner Detroit Edison Company Project Manager - Fermi 2 2000 Second Avenue i
The Detroit Edison Company Detroit, Michigan 48226 l
2000 Second Avenue i
Detroit, Michigan 48226 Mr. Larry E. Schuerman
. Detroit Edison. Company.
3331 West Big Beaver Road i
Troy, Michigan.48084
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Enclosure EDISON /NRC MEETING 19-81 EF-2 TORUS MODIFICATION PROGRAM OVERVIEW O
EDISON APPROACH;FOR RESOLUTION OF THE MARK I CONTAINMENT PROGRAM.
O INTERIM PUA VERSUS STP P
O CURRENT STATUS 0
DISCUSSION TOPICS
- C/0 LOAD EVALUATION
- POOL SWELL VENT SYSTEM IMPACT
- FATIGUE ASSESSMENT
- PIPING 0
NEED FOR SUBMITTAL PACKAGE I
EDISON APPROACH FOR RESOLUTION 0F THE t'i"'( I CONTAINMENT PROGRAM i
0 INTERIM PUA - EXCEEDED THE STP CRITERIA - REQUIRED EXTENSIVE STRUCTURAL MODIFICATIONS.
O INTERIM PUA MOE!FICATIONS CONTINUALLY RE-EVALUATED AS GENERIC PROGRAM INFORMATION (LDR, NRC ACCEPTANCE CRITERI AT MADE AVAILABLE.
)
O SOME MODIFICATIONS REDESIGNED TO MAINTAIN HIGH POTENTIAL FOR SATISFYING LTP ACCEPTANCE CRITERIA (EXAMPLES:
SADDLES, VENT LEADER DEFLECTOR).
O ALL CURRENTLY IDENTIFIED MODIFICATIONS INSTALLED BY FUEL LOAD.
O LTP-PUA ACTIVITIES HAVE BEEN INITI ATED - REPRESENTS A SUBSTANTIAL EFFORT (100,000 MANHOURS) - THEREFORE, EDISON HAS BEEN AWAITING FINALITATION OF THE CRITERIA BEFORE PROCEEDING " FULL SPEED AHEAD."
O LTP-PUA ANALYTICAL ACTIVITIES (NOT REQUIRING TEST DATA) COMPLETE BY AUGUST, 1982.
O SUBMITTAL TO STAFF WILL BE MADE IN SEPTEMBER,1982.
i i
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EDISON PROGRAM CONSISTENT WITH OTHER MARK I UTILITIES O
EDISON AN ACTIVE PARTICIPANT OF THE MARK I GENERIC PROGRAM - THEREBY PROVIDING AMPLE OPPORTUNITY TO CONTINUALLY EVALUATE CONTENT OF OUR APPROACH AND ITS PROGRESS.
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0 EDISON'S PROGRESS ON THE LTP-PUA IN TUNE WITH OTHER MARK I UTILITIES.
[
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MODIFICATIONS BEING INSTALLED AT OTHER MARK I PLANTS OF THE SAME NATURE AS THOSE ALREADY l
INSTALLED OR BEING INSTALLED AT FERMI-2.
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- INTERIM PUA VERSUS STP STP INTERIM PUA 1.
LOADS D.L.
(STEEL)
D.L., L.L. & SEISMIC L. L.
(WATER)
P.S.,
CHUGGIhi & SRV SEISMIC P.S.
IMPACT POOLSWELL P.S.
FROTH & FALLBACK V.S. THRUST, LATERAL & INTERNAL PRESSURE SUBMERGED STRUCTURE DRAG LOADS SRV PIPING TRANSIENT LOADS II.
LOAD COMBINATIONS D.L. k t
+ SEISMIC SECTION 4.2 0F INTERIM PUA DOCUMENTS
+ P00LSeb). (DBA)
COMBINATIONS FOR DLS, P.S.,
SRV, CGG,
& THERMAL III.
ACCEPTANCE CRITERIA-FACTOR OF SAFETY OF CODE ALLOWABLE FACTOR SAFETY OF 2 AGAINST FAILURE APPROXIMATELY 4 AG/J.NST FAILURE m
I P
ENRICO FERMI 2 TORUS MODIFICATION PROGRAM MODIFICATION DESCRIPTION AND STATUS MODIFICATION STATUS D.C. to V.H. Intersection Stiffening I.C.
Downcomer Truss I.C.
V.L. to V.H. Intersection Stiffening I.C.
V.H. Supports I.C.
D.C. Shortened to 3' Submergence I.C.
V.H. Deflector I.C.
Monorail Supports I.C.
T Spray Header Supports I.C.
Catwalk Frame and Supports I.C.
Column to Shell Connection I.C.
Mitered Joint Saddle F&I V.B. Penetration Stiffentsg I.C.
Additional Torus Internal Piping Supports I.C.
V.B. Nitrogen Line Routing and Supports I.C.
V.B. Electrical Conduit Routing and Supports I.C.
Thermocouple Conduit Routing and Supports I.C.
Reroute SRV Piping in the Wetwell I.C.
Stirfening for SRV Penetration V.L.
I.C.
SRV V.H. and V.L. Pipe Supports I.C.
SRV Quenchers and Supports P.O.
t I.C. - Installation Complete l
F&I
--Fabrication and Installation currently proceeding l
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- Purchase Order for material, fabrication and delivery to be issued shortly l
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>as-2 TODAY'S DISCUSSION TOPICS
. o C/0 LOAD EVALUATION P
o 'P00LSWELL VENT SYSTEM IMPACT o
FATIGUE ASSESSMENT i
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'O INTERIM ANALYSIS LIMITED TO DOWNCOVER LATERAL LOADS.
- LOAD DEFINITION ONLY RECENTLY FINALIZED 0
LTP DEFINITION OF THE SUPPRESSION CHAMBER C/0 LOAD HAS BEEN ASSESSED.
- USING ANALYSIS RESULTS FROM OTHER SIMILAR MARK I PLANTS.
- USING ANALYSIS RESULTS FROM SIMPLIFIED FERMI ANALYTICAL MODELS.
- ASSESSMENT RESULTED IN MODIFICATIONS TO SUPPORT
- SYSTEM, I.E., MITERED JOINT SADDLES.
- SUBSEQUENT ASSESSMENT WITH SADDLES SHOWED SUFFICIENT SUPPORT SYSTEM CAPACITY EXISTS.
O ASSESSMENT OF DOWNCOMER LATERAL LOADS SHOWED INTERIM LOADS ENVELOP LTP LOADS.
O COMPLETE EVALUATION OF C/O' INCLUDED'IN PUA..
- PUA NOW UNDERWAY.
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VIEW DEVELOPED NO2AAL TO AXEiES OF V. H. AND DOWNCOMER.
Z. V. H. SUPPORT COLUMN DETMLS NOT SHOWN *OR CLARITY, FIGURE 3.2.2-5 DOWNCOMER TRUSS 3.4s
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PEAR DYNAMIC GISPLACEMLNT.AS S U I LT.-S L I D E R
---P E A R DYNAMIC DISPLACEMENT. SADDLE-SLIDER
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SUPPRESSION CHAMBER C/0 LOAD ASSESSMENT RESilLTS 0
STEADY STATE RESPONSE OF FERMI SUPPRESSION CHAMBER IMPRcVED WITH MITERED JOINT SADDLE.
DOMINANT STRUCTURE FREQUENCY INCREASED BY ~
60%
COLUMN LOAD AMPLITUDES DECREASED ~ 145%
0 SUMMATION OF C/0 LOAD HARMONICS RESULTS IN TOTAL VERTICAL REACTION OF ~ 11550 KIPS.
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SUPPRESSION CHAMBER SUPPORT SYSTEM CAPACITIES FOR C/_0, LOAD $
- 0
' INTERIM PUA SUPPORT SYSTEM CAPACITIES UPWARD LOAD 800 KIPS-DOWilWARD LOAD 1400 KIPS 0- SUPPORT SYSTEM CAPACITIES WITH SADDLE UPWARD LOAD-2000 KIPS DOWNWARD LOAD 3000 KIPS O
REACTIONS CAUSED BY C/0 LOADS ARE LESS THAN SADDLE SUPPORT SYSTEM CAPACITIES.
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_C/_0 LOADS ASSESSMENT RESULTS
)
O MAGNITUDE OF DOWNCOMER LATERAL LOADS USED IN INTERIM PUA ENVELOP LTP LOADS.
LTP PRESSURE MAGNITUDE vel 2.1 PSI EQUIVALENT INTERIM PUA PRESSURE MAGNITUDE 6/ 26.5 PSI O
LTP DOWNCOMER LATERAL LOAD DISTRIBUTIONS SIMILAR TO THOSE USED IN INTERIM PUA.
O PRdLIMINARY ASSESSMENT SHOWS DOMINANT DOWNCOMER FRdQUENCY GREATER THAN DOMINANT LOAD FREQUENCY.
O VENT SYSTEM STRESSES RESULTING FROM 'C/0 DOWNCOMER LATERAL LOADS COMPUTED IN INTERIM PUA ARE EXPECTED TO ENVELOP THE STRESSES COMPUTED USING LTP LOADS.
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e CONDENSATION OSCILLATION LOAD ASSESSMENT' CONCLUSIONS O
ADDITION OF MITERED JOINT SADDLE IS EXPECTED TO PROVIDE
'LONG TERM SOLUTION FOR LTP SUPPRESSION CHAMBER.
j RAISES DOMINANT STRUCTURE FREQUENCIES BEYOND MAXIMUM LOAD FREQUENCIES THEREFORE LOWERS RESPONSE.
i MORE EVENLY DISTRIBUTES LOADS THEREFORE REDUCTIONS IN. LOCAL STRESSES ANTICIPATED.
MORE THAN DOUBLES SUPPORT SYSTEM CAPACITY.
O DOWNCOMER. STIFFENING SYSTEM EXPECTED TO BE ADEQUATE FOR LTP DOWNCOMER C/0 LOADS.
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P00LSWELL IMPACT OF THE VENT SYSTEM - OVERVIEW O
SOME AREAS OF VENT SYSTEM OVERSTRESSED FOR INTERIM
-ANALYSIS P00LSWELL LOADS.
O GENERIC EFFORTS PREDICT HIGH LOCAL VENT HEADER STRESSES DUE TO POOLSWELL IMPACT.
O DECISION WAS MADE TO ADD VENT HEADER DEFLECTOR.
QUARTER SCALE TESTS SHOW DEFLECTOR EFFECTIVEL.Y MITIGATES HIGH LOCAL STRESSES.
O ASSESSMENT OF POOLSWELL LOADS SHOWED INTERIM LOADS ENVELOP LTP LOADS, O
COMPLETE EVALUATION OF POOLSWELL INCLUDED IN PUA.
i PUA NOW UNDERWAY, h
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e VENT SYSTEM ASSESSMENT WITH VENT HEADER DEFLECTOR 0
POOLSWELL IMPACT ACCOUNTS FOR MORE THAN HALF 0F TOTAL COMPUTED STRESS IN THE INTERIM PUA.
O INTERIM ANALYSIS POOLSWELL LOADS.
- MAXIMUM PRESSURE OF 15.1 PSI,
- TOTAL APPLIED LOAD OF 200 KIPS.
- FLAT POOL ASSUMED, O
LTP POOLSWELL LOADS (TAKEN FROM PULD),
- MAXIMUM PRESSURE OF 12.0 PSI.
- TOTAL APPLIED LOAD OF 75 KIPS.
- POOL PROFILE LESS CRITICAL.
O VENT SYSTEM STRESSES RESULTING FROM POOLSWELL IMPACT LOADS COMPUTED IN INTERIM PUA ARE EXPECTED TO ENVELOP THE STRESSES COMPUTED USING LTP LOADS.
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LOADS CONTRIBUTION DETERMINED IN THE INTERIM - PUA Stress / Area Total Stress D.L.
Seismic Pool SRV V.S. Disc.
Int.
(KSI)
(%)
Swell (%)
Thrust (%)
Pressure
(%)
Membrane /
22.0 1
3 53 29 10 4
Vent Header Near Vent Line Membrane /
22.0 3
2 63 17 13 2
~
Vent Header Near Mitered Joint b)
o.
FATIGUE ASSESSMENT 0
COMPREHENSIVE BASIS FOR EVALUATING FATIGUE NOT AVAILABLE AT TIME OF INTERIM PUA.
O EMPHASIS OF INTERIM PUA PLACED ON SHORT TERM SAFETY NOT LONG TERM EFFECTS SUCH AS FATIGUE, i
CONSISTENT WITH STP. APPLIED TO OPERATING MARK I'S,
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O NO EVIDENCE OF FATIGUE PROBLEMS ENCOUNTERED AT FSTF.
O NO EVIDENCE OF FATIGUE PROBLEMS ENCOUNTERED IN OPERATINGIMARK I's, O
FATIGUE EFFECTS FULLY ADDRESSED IN PUA.
NOW UNDER WAY, l
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oe INTERIM PUA FATIGUE ASSESSMENT 0
FOR CHUGGING THE PREDICTED LOAD DURATION AND FRF.QUENCY IDENTIFIED 6000 STRESS CYCLES.
O COULD ACCOMMODATE 2000 SRV' ACTIVATIONS BEFORE ATTAINING A USEAGE FACTOR OF 1.0.
O BASED ON OPERATING HISTORY OF OTHER PLANTS 2000 ALLOWABLE SRV ACTUATIONS' EXPECTED TO EXCEED ANTICIPATED SRV ACTUATIONS OVER 40 YEAR PLANT LIFE.
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p ~s :er EF2 TORUS ATTACHED PIPING 0
SCHEDULE ~FOR PIPING REQUIRED ANALYSES TO BE PERFORMED BEFORE TORUS LOADS AND TORUS ANALYSES FINALIZED.
O STATIC DISPLACEMENT OF 0.25 INCHES INCLUDED IN EQUATION 9 FOR UPSET AND EMERGENCY ALLOWABLES.
CONSISTENT WITH STATIC ANALYSIS APPROACH FOR SEISMIC LOADS.
BASED ON AVAILABLE ANALYTICAL DATA FOR POOLSWELL LOADS.
COMBINED WITH SEISMIC INERTIA BY ABSOLUTE SUM.
0 INTERNAL PIPING EVALUATED FOR SUBMERGED STRUCTURES LOADS.
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"EETING SUMM RY DISTRIBUTION G. Lear Docket File NRC PDR JW 4 M
Johnsk$nckf
. Paw Local PDR _ l V. Benaroya TIC /NSIC/ Tera Z. Ros toczy N. Hughes W. Haass LB#1 Reading D. Muller H. Denton R. Ba'llard E. Case D. Eisenhut W. Regan D. Ross
/
R. Purple P. Check B. J. Youngblood A. Schwencer Chief, Power Systems Branch
- 0. Parr F. Miraglia J. Miller F. Rosa W. Butler G. Lainas R. Vollmer W. Kreger R. Houston J. P. Knight Chief, Radiological Assessment Branch
- 3. Bosnak L. Rubenstein F. Schauer T. Speis R. E. Jackson LKintner Project Manager MSrinivasan Attorney, OELD J. Stolz M. Rushbrook S. Hanauer W. Gammill 01E (3)
ACRS (16)
T, Murley R. Tedesco F. Schroeder D. Skovholt M. Ernst to NRC
Participants:
R. Baer 4%
b k',p' C. Berlinger s
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/ 'c o CPTan, PTKuo, DTerao, anu 6Kintner K. Kniel G. Knighton fd 38 -
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A. Thadani g"J JUN O 81981* ~8 b " TO'ia'?A" "G)
, Kr r
T D, Vassallo ts ([
P Collins
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D. Ziemann 9'
bec: Applicant & Service 1.ist W
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