ML17055D454
| ML17055D454 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/16/1987 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-63425, NUDOCS 8712280041 | |
| Download: ML17055D454 (18) | |
Text
December 16, 1987 LICENSEE:
In the process of reducing the condensation oscillation loads the licensee stated that existing FSAR information was used.
,The licensee was requested to provide confirmation that the assumptions made in the"model used were bounding, the analysis assumed all energy was deposited in the suppression pool and the analysis did not consider heat sinks.
The licensee was requested to provide information concerning how dead weight and pressure were considered in calculation MS-2155 submitted August 28, 1987.
The licensee was also requested to provide the basis for the different stresses in Tables 2 and 3 in MS-2155.
Docket No: 50-410 DISTRUBTION Y.I.LT Niagara Mohawk Power Corporation (NMPC) PDI-1 Rdg.
ARCS(10)
RCapra HBClayton FACILITY:
Nine Mile Point Nuclear Station, Unit 2 (NMP-2)
EJordan DNeighbors NRCPDR
SUBJECT:
SUMMARY
OF MEETING WITH NMPC ON DECEMBER 7, 1987 JKudrick CONCERNING DOWNCOMERS FOR NMP-2 MHaughey Local PDR CVogan OGC On December 7, 1987 the staff met with representatives of NMPC and their con-
- sultant, Stone and Webster Engineering Corporation (SWEC), to discuss downcomers for NMP-2.
The NMP-2 license contains a schedular exemption until star tup following the first refueling outage to show that the downcomer supports meet the requirements of General Design Criteria"(GDC)2 or provide acceptable supports.
The licensee provided a summary of their reanalysis on May 15, 1987.
Additional information was provided on August 28, 1987 and October 14, 1987.
The staff met with the licensee on December 7, 1987 to discuss these submittals.
In the process of redefining the pool loads on the downcomers the licensee's review was narrowly focused on the effects of pool loads on the downcomers, not the rest of the pool.
Specific attention was paid to the low frequency loads.
Kraftwerk Union (KWU) was employed by the licensee to survey traces and to determine the controlling traces.
The licensee was requested to supply a summary of the methodology used to determine which of the traces were controlling.
The licensee provided a handout at the meeting which is included as Enclosure 1.
A list of=meeting attendees is included as Enclosure 2.
Mary F. Haughey, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II
Enclosures:
As stated cc:
See next page PDI-I y PD CVogan 4 aughey 12/~" /87 12/j( /87
~~i22aO04>
Saba>S
~00<K 05000410
'PDR, DI-I
.6 pra P2
/87
I Y
II g
H,r I
W lt I
v P
1 It Y
II J
Kf IP
Mr. C. V. Mangan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 I
CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner 8 Metterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.M.
Mashington, D.C.
20006 Richard Goldsmith Syracuse University College of Law E. I. Mhite Hall Campus
- Syracuse, New York 12223 Ezra I. Bialfk Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 Morld Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 99
- Lycomfng, New York 13093 Mr. Gary Wilson, Esquire Niagara Mohawk Power Corporation 300 Erfe Boulevard Mcst
- Syracuse, New York 13202 Peter E. Francfsco, Licensing Niagara Mohawk Power Corporation 301 Plafnffeld Road
- Syracuse, New York 13212 Don Hill Niagara Mohawk Power Corporation Sufte 550 4520 East Mcst Highway
- Bethesda, Maryland 20814 Regional Administrator, Region I U.S. Nuclear Regulatory -Cotmissfon 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Paul D. Eddy New York State Public Serice
,Comfssfon Nine Mile Point Nuclear Station-Unit II P.O.
Box 63
- Lycomfng, New York 13093 Mr. Rfchard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Mashfngton Avenue
- Albany, New York 12210 Mr. Richard Abbott, Unit 2 Station Super fntendent Nine Mile Point Nuclear Station Niagara 'Mohawk Power Corporation P. 0.
Box 32
- Lycoming, NY 13093 Mr. Thomas Perkins, General Supt.
Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.
Box 32
- Lycoming, NY 13093
LIST OF MEETING ATTENDEES DECEMBER 7, 1987 DOWNCOMERS NAME Nary Haughey Y. C. Li Jack Kudrick MarQ Durka Ed Klein T. L. Wang ORGANIZATION NRC NRC/EMEB NNPC/Licensing SWEC NMPC SWEC
BACKGRMND FR~TED CONDITION Dawncomer design margin not adequate (GER on the Downcomer Design, M-rch 1986)
SQLUTION
LOAD GENERATION REFINEBEZZ SRV Load Reduction CO Load Reduction INCOMER REANALYSIS AND REDUCTION REPORT SUBMITTED ON 4-29-87 Aiditional information regarding the raised Downcomer analysis submit.tted oa 10-14-87 (NMP2L.1083)
Dvwncomer Reanalysis used the same mod& and the same method.
Tee only changes are SRV and CO Loads m the faulted condition.
S:"V LOAD REDUCTION REFINEMENT BASES Use the Generic'Mark II SRV Load Definition instead of the alternate SRV Load Definition (KJREG 6802)"
Use,the Data Base for the quencher and Mark II Geometry Use the NUREG 0802 Frequency Adjustment and pressure multiplier procedure Multiplier is defined. by KPC Change is made only for the faulted condition for basic CO and single SRU Combination Controlling trace is KTG 11.1
CO LOAD REDUCTlON REFINEMENT BASES Use the LaSaH.e plant's pool temperature cut-off procedure which was accepted by HUREG 0808.
No change in data base (Still use 4TCO)
No change in method or Model
~ The only difference is to eliminate irrelevant CO data above plant specific temperature cut-off.
POOL TEMPERATURE LIMIT DETERYENATION Pool temperature cutt-off is determined from the basic CO Load vent mass flux cut-o f of' ibm/ft /sec (NEDE>>24811-P) 2 A
Most severe pool temperature at the vent mass f~~
cut-off is used 119 F for recirc line break Additional margin of.11'F is added as compared to the 5 F margin used
'y LaSalle and accepted by NUREG 0808.
PMA~TERS NINE MILE UNIT 2 WPPSS UNIT 2 LA SALLE UhZT 1,2 Design Power 3,467 Q&t) 3,462 3,434 Blowdown rate from break is expected to be identical Stean Dome Pres+are (psig) 1,040 1,020 1,025 Blowdown rate from break is expected to be identwal Vessel Inside Diameter (Inches) 251 251 Blowdown rate from break is expected to be identi"al Vessel Inside Heigh-(Inch s) 869 875 875 Blowdown rate from break is expected to be identi"al Recirculation Pipe Size (Inches) 24 24 Blowdown rate from br ak is expected to be ident~-al Number Of Jet Pumps Main Steam Pipe Size (Inches) 20 26 20 26 20 26 Blowdown rate from break is expected to be ident~-al Blowdown rate from br=-ak is expected to be identi"al Dryw~t Volum (Cub~- Feet: )
303,400 200,500 22K,500 The temperature rise =ate is expected to be lower =elative to WPPSS/La Salle Miniman Supp.
192,000 Channber Volune (Cuft) 142;500 166,400 Minimun Supp.
145,500 Pool Volume (Cuftj 137,200 142,200 The larger pool voluna will lower the pool temper=-ture rise Downcmner 9.5 to 9.11 11.7 to 1'2 12.8 Submergence
'Feet)
Downanmer
- 2. 37 Resismnce Coefficient 2-77 1.9 No. Of Down-comers (24 size) 121
. 99 98 Lower steam mass flux is expected Pool Temperatur 90
'uring Normal Operation (deg F) 90 100 The NMP2 pool tempera=ure is expected 'to be 10'F Lwer than La Salle
4'
DOWNCOMER FUNCTIONAL CAPABILITYSTRESS SUKfARY LOAD CASES FAULTED 03NDITION MODEL (AO)
Wn=l.94 HZ REVISED FAULTED CONDITION MODEL (AO)
Wn 1.94 HZ SEISMIC INERTIA AND SLOSHING (a)
OBE (b)
SSE 14.46 14.46 (a)
SRV SS LOAD 12.08 FAULTED '1 16.48 FAULTED 2 8.2 FAULTED 1 16.48 PAULTED 2 (b)
SRV ARS 0.20 0.20 (a)
CO SS LOAD (b)
CO.ARS 23.00 0.68 18.15 0.68 (a)
CHUG. LAT.
LOAD 8.49 8.49 (b)
CHUG.
SS LOAD (c)
CHUG.
ARS 8.79
- 0. 90 8.79 0.90 AP ARS 0.30 0.30 TO~~
COMBINED STRESS 30-34 PAULTED 1
25.68 FAULTED '.
25.18 FAULTED 2 25.68 FAULTED Z FUNCZIONAL GAP ABILITYALLOWABLE 31.26 FAULTED 1 30.17 PAULTED 2 31.26 PAULTED 2 30.17 FAULTED 2
P