ML19308C365
| ML19308C365 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/31/1979 |
| From: | Odar F Office of Nuclear Reactor Regulation |
| To: | Phillips L Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-09, REF-GTECI-IS, TASK-A-09, TASK-A-9, TASK-OR NUDOCS 8001230023 | |
| Download: ML19308C365 (46) | |
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- ,cw Ut.G 31 13/9 TMI-2 Generic Task
- A-9 MEMORANCUM FOR:
L. E. Phillips, Acting Chief, Analysis Branch, DSS FRCM:
F. Odar, Analysis Branch, DSS
SUBJECT:
SI'00KHAVEN NATIONAL LABORATORY TRIP REPORT -
NC VEMBER 29-30, 1979 The purpose of the trip was to discuss 1) two types of audit calculations performed by SNL in order to assess inpact of a) overcooling transients on 3&W reactors and b) ATWS events on all reactor vendors and 2) to review the development of the IRT and RAMONA computer programs.
1.
Audit Calculations - Overcoolina transients for B&W reactors 3rcokhaven National Laboratory performed three analyses of overcooling transients for a typical Sabcock & Wilcox 177 fuel assembly plant using the IRT code.
In these analyses it was assumed that the turbine has tripped and ICS has failed to function properly in such a way that the feedwater was continuously pumped into both steam generators. When the ECCS was actuated the main coolant pumps were tripped as per the new requirement by S&O task force. Three cases were run:
a) Mcdeling of the upper head was emitted.
Its volume was included in the upper plenum.
b) Modeling of the upper head was included but the modeling metal heat capacity in the uccer head was ignored.
c) The uoper head and its metal heat capacity were modeled.
i In case a) the system pressure dropped significantly to allow boiling in the primary system.
In cases b) and c) the pressure remained high enough to prevent boiling in the primary loop except in the uocer head.
Enclosure 1 presents the plots of these three cases.
2.
ATJS Audit Calculations - Unresolved iafety Issues A-9 The program and the scope of calculatiois were discussed with the represen-l tatives of 3attelle Columbus (Dr. Robe.t Collier). Due to an increase in l
power level in CE plants to 2710 Mwt, a new steady state initialization is required.
In addition, some code uo;ating such as inclusion of a two phase 800123o 0 2.
s.,
0-
.~
L. E. Phillips pump modeling will also be required. These additional work requirements will cause some delay in the program. The new schedule which was provided by Battelle after the meeting, is presented in Enclosure 2.
The new schedule calls for a completion of the PWR ATWS work by May 30, 1980.
The BWR audit calculations which are being cerformed by BNL, are on schedule.
BNL will modify the RELAP3B code to include slip in the core aP correlation in order to verify the results obtained from the TWIGL code.
Form 189 from BNL does not include any task for any new modification of the codes for ATWS analyses.
If a substantial effort is required, NRC may have to issue a program redirection letter.
3.
Cevelocment of IRT Code 3.1 Status of OTSG !=orovement a.
Mark I version is complete and has been imolemented in the IRT code.
l b.
Modeling of the Mark II versico aill be completed by January 31, 1980.
The implementation will be completed by February 28, 1980.
3.2 Status of UTSG Imorovement Improvement of UTSG will be based partially on the concects used in the BOILER code. These improvements should be compatible with the numerics of the IRT code. The following tasks and schedule were agreed upon:
Task Comoletien Date a.
Investigation of feasibility March 1, 1980 b.
Completion of modeling August 1,1980 c.
Implementation in IRT January 1, 1981 3.3 Verification of the IRT Code The code will ve verified using test data. The following tasks and schedule were agreed upon:
a.
Verification of Mark II OTSG model using data from TMI-2 event - completion l
date: September 1,1980.
5.
Verification of the code using other available plant data - completion date:
Sectember 30, 1980.
3.4 Octional Momentum Ecuatien The code will be modified to include an optional momentum ecuation for a single phase fluid - comoletion date: August 1,1980.
f s-DEC 311979 L. E. Phillips
-3_
3.5 Imoroved Inout and Outout Edits The code will be modified to include i.. proved output and input edits -
completion date: July 1, 1980.
4.
Imolementation of the RETRAN Codi The code will be modified and verified using available plant data as cer NRC request at a later date.
5.
Develocment of the RAMONA Code The following tasks and schedule were agreed upon:
Task Comoletion Date I.
Code Assessment and Imorovement a.
Code assessment against test April 1, 1980 data (including Peach Bottom tests) b.
Proposal for improvements, May 1, 1980 definitions of necessary tasks to creduce an adequate code and schedules c.
Implementation of Item b above September 30, 1980 and beyond II. Addition of Small Break LCCA Cacability a.
Assessment of code adequacy and April 30,1980 proposal for necessary modi-fications and subtasks such as modeling of break flow and ECCS with detailed schedules (assess-ment will include a comparison of advantages and disadvantages over a small break RELAP code) b.
Imolementation of critical flow April 30, 1980 models for feedline, steamline and recirculation icop breaks c.
Comolete implementation of the September 30, 1980 and beyond subtasks defined in Item a acove I
s.
e.
DEC 311979 L. E. Phillips 4
Task Completion Date III. Reauired Code modifications for Licensing Calculations a.
Complete implem!ntation of January 31, 1980 the jet pump ani recircu-lation loop models b.
Modeling and impiementation of plant dontrol cnd pro-tection system i.
Identify subtasks to April 1, 1980 model systems and prepare models and schedules for their implementation 11.
Completion of imple-September 30, 1980 and beyond mentation of the sub-tasks c.
Implement Reactivity Edit August 30, 1980 Capability
~
/
Fuat Odar Analysis Branch Division of Systems Safety Enclosures
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s ENCLOSURE 1 Overfeeding Transient for a B&W 177 Fuel Assembly Plant l
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.w, Figure 1 IRT Primary Systen Nodalization
?a' Generator Steam Generator i
Pressurizer 11 10 I
4 5
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B & W Overfeed Transient Event Sequence Event Time (Seconds)
Power = 100%
Initial conditions Flow = 100%
Initial conditions Pzr pressure = 2157.8 psia Initial conditions Turbine trip initiated 0
Turbine flow ramps to zero 0 - 2.5 sec.
.5 sec.
ICS Fails F.W. stays on Aux. F.W. ramps to 4.1%
1 - 4 sec.
Peak Pzr pressure = 2232 psia 5.4 sec.
Pzr empties (PPzr = 1589 psia) 42.7 sec.
ECCS trip (at P = 1615) 41.5 sec.
Pump trip (on ECCS trip) 41.5 sec.
ECCS delivery (after 6.4 sec. delay) 47.9 sec.
Upper head flashes 42.5 sec.
Candy cane flashes Between 45 and 50 sec.
Candy cane quality =.001 50 sec.
Max. candy cane quality =.0088 s 105 sec.
void =.28 (HEM)
Pressure falls Continues I
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ENCLOSURE 2 Schedule for pyR ATWS Analysis I
1
o e,
TAlli.E l. SCilEI)UI.E FOR 'NIUS TRANSIENT CASES FOlt TilREE IHR llESICNS 9
RIMCTOR llESIGN WESTINGilullSE COllllllSTION llAllCOCK & Wil.COX llESCR il' TION ORDER
- DATE**
ORDER
- DATE**
ORDER
- DATE**
TYl'E OF CAI.Cill.ATION 1.orW/SoSv 3
3/11/80 3
3/l4/80 2
2/22/80 stase til'IS 6
5/1/80 6
5/5/110 Sensitivity ALMS del.AY 3
3/10/80 Sensitivity SOHV 1
2/1/80 1
2/11/80 1
1 / 31 /110 liase til*lS 2
2/20/80 2
2/25/fl0 Sensitivity SOSV 4
3/ 31 /110 4
4/2/t10 4
3/31/80 liase til'IS 7
5/9/80 7
5/16/80 Sensitivity RCI' 5
4 / 111/110 5
4/22/80 5
4/18/80 Sensitivity 1.001' 6
5/9/80 liase No t e a :
- - Oraler in wl Icle cases will lie carrieil out for eacle alesign
- - Tentat.lve completion. late
O
.o,'. e ORIENTATION g,j j j 11/27 I
l STEADY STATE n TRANSIENTS
_ CASES hC W
o v
l 12/3 1/3
$/9 l
SG STEADY g
A'I'E TRANSIENTS C-E CASES IO O
^
n 12/3 12/21 1/17 s/16 g
SG STEADY HOD STATE TRANSIENTS ll6W CASES n
m v
v l
12/10 12/21 1/9
.j9 l
PilHl' HOD El.
g CODE Hull HODIFICATION J2/5 jfg l
l REPORT k - - - - - - - - - - - - - -
_ _ g 'REPAR AT ION I
REPORT 4/15 s/30 l DEC '/9 3
i a
n a
.lAN '80 Fell '80 MAR '80 Al'R '80 MAY '80 FIGilRE I.
OVF.RAl.l. SCllEDill.E FOR PWH ATWS CAI.Cill.ATIONS
Oc.c 311979 L. E. Phillips Distribution:
F. Scnroeder R. McDermott R. Denise W. Kato (BNL)
S. Hanauer M. Levine (BNL)
R. Mattson W. Shier (BNL)
R. DeYoung W. Wulf (BNL)
D. Ross V. Stello L. Tong D. Eisenhut R. Tedesco Z. Rosztec:y T. Novak S. Fabic K. Kniel P. Check
- 3. Liaw
- 3. Grimes P. Norian S. !srael G. Ma:etis J. Heltemes W. Minners M. Aycock F. Almeter J. Strosnider G. Knightan K. Parc:ewski R. Audette R. Franm
- 3. Sheron W. Jensen F. Odar D. Hunter (Region III)
P. Matthews M. Ruoin E. Throm A. Thadani C. Graves S. Newcerry G. Kelly G. Holahan H. Silver S. Salah S. Weiss D. Fieno M. Mendenca N. Zucer
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