ML19224A890
| ML19224A890 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 05/25/1979 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Mattson R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906120002 | |
| Download: ML19224A890 (7) | |
Text
/
,, p m
---MbQ,.
'I N'
A l
'[
cice. ~.:\\
au r e,
8 UNITED sTAIEs U"
$Y NUCi. EAR REGULATORY COMMISSION bp l% 4t' w d. O ';'
3. ' h, g'. %
b.l h a -a '" N 3
msmNGTON. D. C. W 55 Y se q
i s M ysg !
g + J
.L.tv, L M
^
%, Y f (Taf. i';),?) 2 D1 [
"W 5 1379
/
g MEMORANDUM FOR:
Roger J. Mattson, Director, Division of Systems Safety FROM:
G. Knighton, Chief, Environmental Evaluation Branch, D0R cY THRU:
B. Grimes, Assistant Director for Engineering and Projects, D0R
SUBJECT:
" LESSONS LEARNED" RECOMMENDATIONS FOR POSSIBLE CHANGES TO NUCLEAR POWER PLANTS BECAUSE OF THREE MILE ISLAND ACCIDENT for your consideration is a list of possible changes to nuclear power plants suggested by EEB staff based on their experience with the Three Mile Island accident.
This list is the result of observations made by these personnel during their involvement in responding to the Three Mile Island accident at the Incident Response Center or at the plant site.
The list contains preliminary recommendations which we believe should be considered as part of the NRR program to re-evaluate the safety of nuclear power plants in light of the Three Mile Island accident.
We c'o not believe that all recommendations need to be implemented, but only that they be ccnsidered to assure that plants will have an adequate safety margin.
We are available to discuss the possible chances we have listed in the enclosure. is a table showing the branches we believ should consider the trerits of the possible changes given in Enclosure 1 9
o
/
G. W. Knight 7, valuation Branch Chief Environment E
Division of Operating Reactors
Enclosures:
As stated cc:
See page 2 169 136 7906120 coa
l Roger J. Mattron
.- f cc:
V. Stello D. Eisenhut R. DeYoung W. Kreger R. Denise S. !!anauer R. W. liouston J. Collins Acting Chief, RAB L. Huhran V. Genaroya s
169 137
ENCLOSURE 1 RECC""El:DATIONS FOR POSSIBLE CHANGES T0_
~ e OPERATING REACTORS BASED ON THE THREE MILE ISLAND ACCIDENT 1.
Short Term Action A.
Prevent the containment sump pump from pumping highly radioactive water out of containment and overflowing tanks in the liquid rad-waste systen.
Consideration should be given to:
(a) radiation monitor on discharge of pump to shut down pump; (b) switch to shut off pump when the receiving sump tanks are f ull ;
(c) pump does not autoratically start up af ter containment isolation signal is turned off; (d) interlock sump pump with containment radiation monitors.
B.
Provide additional TLDs around plant to monitor environmental impact (radiation) during first few days of accident.
(a)
Require one TLD in every 22.5 sector at exclusion boundary, 1 mile, 5 miles and 10 miles f rom plant.
(b)
Require additional radioiodine air ronitors offsite.
C.
Have all non-ESF ventilation charcoal adsorber filters cosa 'y with the testing requirements of Regulatory Guide 1.140, " Design, Test-ing and Maintenance Criteria for I;ormal Ventilation Exhaust System 169 138
_r Air Filtration and Adsorption Units of Light-Water-Cooled tiuclear Power Plants." This will provide r. ore assurance that plants will have charcoal filters to filter iodine from contaminated areas not associated with ESF systems.
D.
Install means to drain the secondary side of a steam generator and to process this water without a person having to enter containnent.
This would have allowed the highly contaminated water on the second-ary side of steam generator B to be cleaned up before the steam
-generator was needed to help cool the core.
E.
Pipe up means to vent pressurized waste gas holdup tanks and to pump water in liquid radaaste tanks back to containment.
F.
Pipe up means to pump water in liquid raddaste tanks out to addi-tional tanks outside the plant.
G.
Install shielding in areas where recombiners will be installed to control the hydrogen concentration inside containment.
This will reduce the time needed to install the recombiners before they can be operated.
H.
Require all plants to have an operating radoaste system with no serious leaks before the plant s tarts up af ter refueling.
1.
Install a redundant high range gaseous effluent ronitor on the final ventilation release point which will not be af fected by the background from expected releases of activity during an accident.
169 139
J.- Provide high level alarms for all sumps and tanks in the liquid rad <iaste systems.
K.
Provide as-built piping drawings in the control roon.
- i..
Install a small ventilation charcoal adsorber filter unit for the sarpling area.
M.
Install redundant radiation monitors on the ventilation supply duct to the control room to isolate the control room upon high radiation.
2-L.001.Te_rm Action A.
Require a non-ESF ventilation charcoal filter to be installed 'cr the following systems to reduce releases of radiciodine from these systems during an accident:
(1)
Condenser Air Ejector (2)
Liquid Radaaste Tanks.
B.
Complete Generic Activity A-34, " Instruments for Monitoring Radiation and Process Variables During Accidents." This would provide specific guidance on funct ional and operational capabilities required of the various ir.>truments during an accident.
C.
Review the radwaste system (including available tankage) to determine if the plant could handle the water generatcd in a TMI Accident without processing for 30 days.
D.
llave a meteorological tor.cr on each site with a readout in the control room.
169 140
_4 E.
Install a non-ESF ventilation charcoal adsarber on all ventilation release paths to be able to filter radiciodine from any contaninated area.
f.
Provide additional shielding in the vicinity of the 53rpling area to reduce rarliation levels from adjacent equiprent during an accident.
9 169 141
,Ej CL_0,SURE 2 EDANCHES TO REVIEW POSSIBLE CliANGES TO PLANTS BECAUSE OF TiiE TliREE MILE ISL AND ACCIDENT r
Item Reviewing Branchas 1.A Discussed in IE Bulletin 79-05 1.B RAB/ DSE 1.C ETSB/DSE 1.0 ASB/ DSS; AAB/DSE 1.E EISB/DSE 1.F ETSB/DSE 1.G AAB, RAB/DSE 1.H ETSB/DSE 1.I ETSB, AAB/DSE 1.J ETSB/DSE 1.K EISB/DSE 1.L ETSB, AAB/DSE l.M AAB/DSE 2.A EISB, AAB/DSE 2.B AAB, LTSB/DSE 2.C EISB/DSE 2.0 H"B/DSE 2.E ETSB, AAB/DSE 2.F RAB/DSE 169 142