ML17326B030
| ML17326B030 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/16/1985 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512230312 | |
| Download: ML17326B030 (32) | |
Text
Docket Nos.:
50-315 and 50-316 Dgt,] 6 1985 LICENSEE:
FACILITY:
SUBJECT:
Indiana and Michigan Electric Company (IMEC)
Donald C.
Cook Nuclear Plant, Units I and 2
SUMMARY
OF MEETING HELD ON DECEMBER 5, 1985 WITH IMEC TO DISCUSS HYDROGEN CONTROL PROGRAM The staff met with the licensee and their representatives from Westinghouse and Battelle Columbus to discuss the status of the hydrogen control program at D.
C.
Cook to meet the requirements of 10 CFR 50.44.
The list of attendees is enclosed as Enclosure l.
The licensee's and their representative's presentations were made from the viewgraphs enclosed as Enclosure 2.
The hydrogen/steam source term is being generated by the MARCH 2. 151 code by Battelle Columbus.
Westinghouse will perform the containment response calculations using the CLASIX code.
The accident scenarios being investigated are of concern to the staff as to whether the set of sequences chosen for containment response analysis (tem-perature and differential pressure) is appropriate and whether the amount of ice melted plays a significant role in the result.
Of particular staff concern is whether a small or intermediate break LOCA with failure of ECCS in the recirculation mode (S2H or SIH) may produce a chall'enge to 'contain-ment beyond that proposed by the licensee.
As a result of the discussions, the licensee will proceed with their program as 'outl'i'ne'd'and"at'he c'onclusion of the CLASIX runs, the licensee will present a position on the need (or lack) for an S1H/S2H calculation.
This posi'tion would b'e available the 24th'week or by February 28, 1986 on the current schedule.
The licensee will also make available in the near future the results of the MARCH 2 runs.
For the CLASIX runs, the licensee will first reassess the fog formation studies and results to determine the impact of a reduced spray drop removal efficiency on the CLASIX hydrogen combustion assumptions.
The need for a detonation cal-culation will be made following the fan failure determination in week 20.
The overall schedule leading to a program plan and schedule for addressing equip-ment survivability is still to be accomplished within 44 weeks but the individ-ual dates have been somewhat adjusted.
The schedule is acceptable to the staff noting that any decision to consider SlH/S2H may affect the overall schedule.
ORIGIN SIGNEDBXC
Enclosures:
As stated D. L. Wigginton, Project Manager PWR Project Directorate b4 Division of PWR Licensing-A, NRR DISTRIBUTION:
~p PWR R-A BJY gblood 12//
/85 P WR R-A DWigginton:kab 12/ /~5 8512230312 851216 PDR ADOCK 05000315 P
r, II 4
~
I l
W id E
I'
Mr. John Dolan Indiana and Michigan Electric Company BEG 1 6 1985 Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation I Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 W. G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvi 1 le, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, DC 20036 Mayor, City of Bridgeman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room I - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation I Riverside Plaza
- Columbus, Ohio 43216
ENCLOSURE I HYDROGEN CONTROL MEETING DECEMBER 5, 1985 D. Wigginton J.
E. Rosenthal K. I. Parczewski R. L. Palla C.
G. Tinkler ORGANIZATION NRR/PWR¹4 NRR/RRAB NRR NRR/DSRO/RIB NRR/PSB Mark Leonard Tom Crawford Jim Feinstein Hussein Fouad Pete Morris Ray DiSalvo Lynn Connor Battel 1 e Columbus DEP AEP AEPSC Westinghouse Battelle Columbus Doc-Search Associates
SEVERE ACCIDENT ANALYSES.
A BASIS FOR RESOLVING ISSUES CONCERNING HYDROGEN CONBUSTION AND CONTROL AT DONALD Ce COOK NUCLEAR PLANTS HID-PRQGRN REYIEM DECENBER 5, 1985 AEP
-:.'.'.Ballelle Cot umbus laboratories
PROGRAM PLAN SCOPE
~
CALCULATE THE RANGE OF PHYSICALLY REALISTIC HYDROGEN SOURCE TERMS FOR SEVERAL REPRESENTATIVE ACCIDENT SCENARIOS
~
DETERMINE.THE TIME DEPENDENT DISTRIBUTION OF H2 AND PRESSURE TEMPERATURE LOADS IN CONTAINMENT POSSIBLE RECIRCULATION FAN FAILURE ROUTING OF HIGH POINT VENT LINE
~
EXAMINE THE POSSIBILITY OF DEVELOPING GAS COMPOSITIONS THAT REQUIRE CONSIDERATION OF LOCAL DETONATIONS
~
IF DETONABLE COMPOSITIONS ARE PREDICTED'EFINE THE TRANSIENT PRESSURE HISTORIES (FORCING FUNCTION) FOR CONTAINMENT STRUCTURE DYNAMIC ANALYSIS
~
BETERMINE THE POTENTIAL FOR REDUCED IGNITER EFFECTIVENESS DUE TO SPRAY IMPINGEMENT OR GAS VELOCITIES AEP
'.",.",.'.Battelle
'olumbus laboratories
)'
(1
ANALYTICALTOOLS
~
HYDROGEN/STEAN SOURCE TERMS 0
CONTAINMENT RESPONSEt
~
DETONATION PRESSURE RESPONSE~
MARCH 2 CLASIX CHAPMAN JOUGUET THEORY AEP 0BBIIelle Columbus Laboratories
APPROACH FOR DEVELOPING H /H 0 SOURCE TERNS
~
SELECT SET OF ACCIDENT SCENARIOS THAT COVER REPRESENTATIVE RANGE OF GAS RELEASE RATES TO THE CONTAINMENT LOW PRIMARY SYSTEM PRESSURE
=
S]D'NTERMEDIATE PRIMARY SYSTEM PRESSURE
= S2D HIGH PRIMARY SYSTEM PRESSURE
= TNLU' TIME OF RESTORED COOLANT INJECTION WILL BE TREATED PARAMETRICALLY TO ALLOW SEVENTY FIVE PERCENT ZIRCONIUM OXIDATION
~
ONLY CORE DEGRADATION SCENARIOS WILL BE CONSIDERED (RESTORATION OF ECC IS ASSUMED TO ARREST ZR OXIDATION AND PREVENT CORE MELTDOWN)
AEP
":".",.'.Baffelle Coluiut>us Laboratories
PRELININARY RESULTS OF DONALD C.
COOK NARCH CALCULATIONS TIME AT TIME TO WHICH CORE RCS PRESSURE CORE NELTING AT BEGINNING SEQUENCE UNCOVERY BEGINS OF CORE NELT (MIN)
(MIN)
(PS IA)
TIME AND RATE AT WHICH COOLANT INJECTION IS RESTORED (MIN)/(GPM)
NAXIMUM RATE OF HYDROGEN RELEASE
. (LB/MIN)
TOTAL FRACTION OF ZIRCONIUM OXIDIZED (K)
=-
TNLU'1D'2D'3.
5.
22, 59, 19,.
37, 23(NF),
24.
1266.
75,/1100, 50./500, 43./550,
- 217, 434,
- 166, 75.1 73,0" 75,9 "TO BE INCREASED TO 75K IN FINAL CALCULATION PRIOR TO CLASIX ANALYSIS
- ",.".::HaNelle Columbus Laboratories
3000.0 p2500.0 pf DONALD C.
COOK NUCLEAR PLANTS Restore ECCS 2000.0 1500.0 oooo.o 500.0 0,0 0.0 20.0 40,0 60,0 SyD'pD'NLU'eginning of clead oxidation Restore ECCS 80.0 i00.0 i20.0 i40.0 i60.0 i80.0 200.0 TIME (MINUTE)
120.0 DONALD C.
COOK NUCLEAR PLANTS 100.0 80.0 g
60.0 40.0 M
l l
l 1
l l
l I
l l
l l
l Sqo'eIief VaIve EIevation 20.0 Break EIevation Top of Active Core 0.0
. 0,0 20.0 40.0 60,0 80.0 100.0 120.0 140.0 160.0 180.0 200.0 TIME (MINUTE)
2000,0 DONALD C.
COOK NUCLEAR PLANTS A
,O 1500.0 1000.0 500.0 Restore ECCS I
I I
I r
I I
I l
I I
I I
f I
SyD'pD't1LU'.0 0.0 20.0
//II/
40.0 60,0 80,0 100.0 120.0 140.0 160.0 180.0 200,0 TrME (err NUTE)
DONALD C.
COOK NUCLEAR PLANTS TNLU' CLAD REACTED
~ eeeeeeee CQQg 0.8 0.6 0.4
~ee
~
~
~
~
~ e~
~ e e
0.0 0.0 80.0 40.0 60.0 80.0 100,0 120.0 140,0 160.0 180.0 800.0 TIME (MINUTE)
1.0 DONALD C.
COOK NUCLEAR PLANTS S1D' CLAD REACZED
CORE MELTED 4.
08 0.6 O
0.4
~ +
~I
~ yf
~ ~ ~
~ ~
~ 0
~t
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~ ~ tg
~
~ +
~O
~l
~ 1 02 0.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 TIME (MINUTE)
1.0 DONALD C.
COOK NUCLEAR PLANTS S2D' CLAD REACTED o
~
o oooo g)gg gfgg)
~
'.8 0.6 O
0.4 o+
~
~
~
~
~
~
~
~
~ oo ~
~ o
~ oo
~o 02 0.0 Q.O 1Q.O 2Q.O 30.0
. 40.0 50.0 60.0 VO.O TIME (MINUTE) 60.0 80.0 100.0
Kl O
O O
A 1000.0 800.0 600.0 400.0 200.0 0.0 0.0 I
11llllll I
1 I iii l
I I
I I
20.0 40.0 60.0 DONALD C.
COOK NUCLEAR PLANTS TNLU'0.0 25.0 Hydrogen Steam 20.0 15,0 10.0 Il II I1 l
L I
I (l
5.0 0.0 140.0 160.0 180.0 200.0 80.0 100.0 120.0 TIME (MINUTE) t O
O
1000.0 DONALD C.
COOK NUCLEAR PLANTS S1D'0.0 800.0 25,0 O
O O
Cl 600.0 400.0 200.0
)1l IIIl IIiltlIIIl I l I l I
I l
l Hydrogen Steam 20.0 15.0 10.0 5.0 O
,O O
O 0.0 0.0 20.0 40.0 60.0 0.0 80.0 100.0 120.0 140.0 160.0 180.0 200.0 TIME (MINUTE)
OO O
O 1000.0 800,0 600.0 4$.0 200,0 0.0 I I
~
I("
I I
I DONALD C.
COOK NUCLEAR PLANTS S29'ydrogen Steam 30.0 25.0 20.0 15.0 10.0 5.0 0.0 O
g 0.0 20.0 40.0 60.0 80.0 100,0 120.0 140.0 160.0 TIME (MINUTE) 180.0 200.0
p
25.0 DONALD C.
COOK NUCLEAR PLANTS TllLtj'0.0 O
5.0 0.0 0.0 20.0 40.0 60.0 80,0 i00.0 f20.0 i40.0 i60,0 i80.0 200.0 TrME (MrNUTZ)
MCH CONTAINNENT RESPONSE CALCULATIONS
~
RFSULTS PROVIDE PNl Y A PRELIMINARY ESTIMATE OF CONTAINMENT RESPONSE
~
CONTAI NMENT MODELING IS SIMPLISTIC YERY COARSE NODAL IZATION INTERCOMPARTMENT FLOWS BASED ON PRESSURE EQUILIBRATION
~
RESULTS AID IN ANTICIPATING QUALITATIVE DIFFERENCES IN CONTAINMENT
RESPONSE
AMONG DIFFERENT SEQUENCES
- ".','.Baltelle Columbus Laboratories
28.0 DONALD C.
COOK NUCLEAR PLANTS TNLU'6.0 24.0 22.0 20.0 18.0 16.0 PRELINIHARY DETAILED ANALYSIS TO BF.
PERFORMED HITH CLASIX a4.0 0.0 20.0 40.0 60.0 80.0 100.0 5$.0 140.0 160.0 180.0 200.0 TIME (MINUTE)
1600.0 DONALD C.
COOK NUCLEAR PLANTS TNLll'
" o
~\\
OO 600.0 1600.0 1400.0 1200.0 1000.0 400.0 200.0
~ s ~ ~
~o I
~ s ~
' ~
~o s ~ ooososo so ~
~ ~
~ ~
~ ~ o ~ o ~ o ~ ~ s ~ s
~ s ~ ~ ~ oosoooooooo
~ ~ ~ ~
s ~
I I
II II Ii I
II s II IIlI IIII iI I
( III I
IIII III Ili III III III l"
I I
I I
I
~ o os
~ Oooo~
loss)
~ ~ ~ ss ~
DEAD END REGIONS
LOEt COMPARTlBR I.C. UPPER PLZÃJM UPPER COMPKGXBEIT PRELININARY DETAILED ANALYSIS TO BE PERFORMED WITH CLASIX 0,0 0.0 20.0 40.0 60.0 60.0 100.0 120.0 140.0 160.0 180.0 800.0 TIME (MINUTE)
RB.O DONALD C COOK NUCLEAR PLANTS S2D'8.0 84.0 REO 80.0 18.0 16.0 PRELININARY DETAILED ANALYSIS TO BE PERFORMED HITH CLASIX 14,0 0.0 io.o 80.0 30.0 40.0 50.0 TIME (MINUTE) 60.0 90.0
oooo>>
o 1600.0 1400.0 DONALD C.
COOK NUCLEAR PLANTS S2D' DEhD END REOIONS
LOlKR C01PARTMEHV I.G UPPER FLEHUM UPPER COMPARTMENT 1800.0 S4 f4 O
1000.0 600.0 600.0 400.0 200.0 PRELININARY DETAILED ANALYSIS TO BE PERFORNED HITH CLASIX
~ >>o ~ os>>os>>>>
~ s>> ~ oos ~ ooo ~ s ~ ~ o ~ o ~
~
~ oo ~ o ~ oo ~ o ~ >> ~ >> ~ >> ~ o
~o
~ o ~ ~ ~ o ~ >>
~
~
~
oo ~ sooooosoo
~
~ os>>>>
~ ~
~ >>
ooo>>so>>s
~
~
>> ~
>> ~
>>>>o
~ >>oooo>>
IIIIIlI I
I I ~
I I
\\
I
~
~
I I
.o>>i>> ~ s$
I I
I I
I
~Is ~ ~ o ~ ~ o
~ ~ ~ ~ >> ~ ~ ~ >>>>os
~
\\
~
ossian
>>ooo ~ s 0.0 0.0 10.0 20.0 30.0 40,0 50.0
~Mz (MINUTED 60.0 70.0 80.0 90.0
40.0 DONALD C.
COOK NllCLEAR PLANTS SID'5,0 30.0 25,0 20.0 15.0 PRELININARY DFTAILED ANALYSIS TO BE PERFORNED WITH CLASIX 10.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 60.0 90.0 100.0 110.0 TIME (MINUTE)
DONAlD C.
COOK NUCLEAR PLANTS S1D'f C4
-W OO 8000.0 1500.0 1000.0 500.0
DEAD END REGIONS
LOVER COMMTMENT LC. UPPER PLENUM UPPER COEPARTIDEIT PRELININARY DETAILED ANALYSIS TO BF PERFORMED WITH CLASIX 0.0
~ Pitteyy ~ ~ ay
~ ~ ~
~ + ~ too>i~ ++
~
0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t1 ~ 1 ~ ~
4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ o sjo ~ ~ ~ ~ ~
~ ~ ~ ~ 0 ~ 0 ~ ~
~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
O.O 1O.O aO,O 3O.O 4O.O 5O.O 6O.O VO.O eO.O eO.O aOO.O 110.0 TIME (MINUTE)
SUNNARY
~
NARCH CALCULATIONS FOR THREE BASELINE SEQUENCES HAVE BEEN COMPLETED 0
HYDROGEN/STEAM RELEASES ARE TIME DEPENDENTS PHYSICALLY CONSISTENT'ND VARY SIGNIFICANTLY AMONG THE SEQUENCES CONSIDERED
~
75K IN VESSEL ZIRCALOY OXIDATION ACHIEVED IN EACH SEQUENCE
~
'ELASIX CONTAINMENT ANALYSES IN PROGRESS
~ -
INVESTIGATION OF IGNITER EFFECTIVENESS IN PROGRESS AEP
'.,'.BaHelle Columbus Laboratories
SCHEDULE OF REMAINING ACTIVITIES
~
HESTINGHOUSE BEGINS WORK WITH CLASIX C
DELIVER CLASIX INPUT FOR REVIEW WEEK 12 14 DATE 12/06/85
. 12/20/85
~
EFFECTS OF SPRAY IMPINGEMENT ON IGNITER EFFECTIVENESS 16 01/03/86
~
RECEIVE APPROVAL OF OR MODIFICATIONS TO CLASIX INPUT
~
PROVIDE RESULTS FROM INITIAL SET OF CLASIX ANALYSES (BASE SEQUENCES)
'20 01/03/86 01/31/86 0
DETERMINE NEED TO EVALUATE DETONATIONS AND RESULTING DETONATION LOADS FOR DYNAMIC "CONTAINMENT ANALYSIS 20 01/31/86
. ~
FINAL REPORT ISSUED BY BATTELLE NRC NOTIFICATION OF FINAL RESOLUTIONS OF BATTELLE WORK ALONG WITH PROGRAM PLAN AND SCHEDULE ADDRESSING EQUIPMENT SURVIVABILITY
~
DETERMINE IF RECIRCULATION FAN FAILURE IS
-POSSIBLE
~
REPORT EFFECTS OF FAN FAILURE IF POSSIBLE
~
INTERIM PROGRAM REVIEW WITH NRC FINAL CLASIX REPORT TO BATTELLE
.DRAFT REPORT ISSUED BY BATTELLE AEPSC REVIEW OF DRAFT REPORT 20 22 24 25 30 36 40 01/31/86
, 02/14/86 02/28/86 03/07/86 04/11/86 05/23/86 06/20/86 07/18/86
'".".'.Battelle Columbus Laboratories
H, 4'k, <.t'ie 4 MEETING
SUMMARY
DISTRIBUTION Docket File NRCPDR t
PDR NSIC PRC System PWRk'4 Reading File Project Manager M. Duncan
- Attorney, OELD J. Partlow E. Jordan B. Grimes ACRS (10)
D.
Wi qinton NRC Partici ants D. Wigginton J.
E. Rosenthal K. I. Parczewski R. L. Palla C.
G. Tinkler OTHERS bcc:
Licensee 8 Service List