tritium in the demin water system -- an ie bulletin 80-10 challenge ken sejkora entergy nuclear...
TRANSCRIPT
Tritium in The Demin Water System --
An IE Bulletin 80-10 Challenge
Ken SejkoraEntergy Nuclear Northeast – Pilgrim Station
Presented at the 12th Annual RETS-REMP WorkshopAtlantic City, NJ: 24-26 Jun 2002
Problem Identification Detected tritium in October sample from
station heating system: 3E-6 uCi/mL Previous samples historically showed
NDA; follow-up sampling indicated upward trend
Response delayed by lack of on-site H-3 analysis capabilities… delays through vendor lab
Initiated IE80-10 sampling of interfacing systems
Problem Scoping IE80-10 sampling detected H-3 in
demineralized water system: 9E-6 uCi/mL DW system analyzed monthly for gamma;
no previous H-3 analysis Follow-up sampling indicated upward trend Initially suspected backflow from interfacing
system; extensive sampling in various legs of DW system yielded ~ equal concentrations… no smoking gun!!
Problem Assessment DW used as makeup to clean systems (diesel
generators, stator cooling); top off lead-acid batteries (mixed waste?); mix chemical standards for clean-area use
Lack of previous H-3 sampling of DW system gave us nothing to compare to… i.e., had the problem existed before, or was it “new”?
Review of system design revealed shared vent line with condensate storage tanks… could we exchange activity through a vent line? H-3…YES!
PNPS has had an eight-fold increase in reactor coolant boron and tritium in past 2 years from control blade leakage… coincidence?
Condensate Storage Tank(one of two)
Demin Water Storage Tank
16” Underground Ventilation Header to Radwaste Building
12” Vent Pipe Internal to CST
4” Vent Pipe Internal to DWST
El. 40’6”
El. 22’2”
275,000 gal.
50,000 gal.
Diagram of Tank Ventilation Cross-connection
Condensate Storage Tanks Two tanks at 275,000 gal each Tritium Concentration = 7E-2 uCi/mL,
total H-3 inventory in CST = 146 Ci Average daily water flux = 33,000
gal/d, 4,400 cu.ft/day Nominal temperature at 80 deg.F,
airborne H-3 = 1.8E-6 uCi/cc air Daily airborne tritium flux = 220
uCi/day
Demin Water Storage Tank One tank at 50,000 gal Tritium Concentration = 2E-5 uCi/mL,
total H-3 inventory in DWST = 0.0038 Ci
Average daily makeup = 2,300 gal/day, 308 cu.ft/day
Nominal temperature ~ outside ambient (45 deg. F in winter)
DWST is heat sink compared to 80 deg. CSTs… effective condensation trap!!
Air Exchange From CSTs
0
500
1000
1500
2000
2500
3000Sep
-01
Sep
-01
Oct-01
Oct-01
Nov-01
Dec-01
Dec-01
Jan-02
Feb-02
Date
Hou
rly A
ir E
xcha
nge:
ft^3
/hr
0
150000
300000
450000
600000
750000
900000
Cum
ulat
ive
Air
Exc
hang
e: ft
^3
ft 3̂/hr ft 3̂
Tritium Exchange From CSTs
0
30
60
90
120
150
Sep
-01
Oct-01
Nov-01
Dec-01
Jan-02
Feb-02
Date
Hou
rly A
ir H
-3
Exc
hang
e: u
Ci/h
r
0
9000
18000
27000
36000
45000
Cum
ulat
ive
Air
H-3
E
xcha
nge:
uC
i
uCi/hr uCi
Proposed Solution Remove source term to DWST by
removing ventilation cross-tie Maintain venting of CSTs to radwaste
building, capture as monitored release Vent DWST to atmosphere, as
radiological concerns disappear following modification
Cannot effectively remove H-3 through treatment… dilution, bleed & feed
Radiological concerns following mod?
Condensate Storage Tank(one of two)
Demin Water Storage Tank
16” Underground Ventilation Header to Radwaste Building
12” Vent Pipe Internal to CST
4” Vent Pipe Internal to DWST
El. 40’6”
El. 22’2”
275,000 gal.
50,000 gal.
Capped End DWST Vent open to Underground Valve Pit
Modified Tank Ventilation Scheme
Projected Dose Consequences Catastrophic failure of DWST, entire
volume released in 20 min as liquid effluent release: 7E-6 mrem to maximum-exposed individual
Evaporation of tank volume released as airborne effluent following vent modification: 6E-6 mrem to maximum-exposed individual
Questions Raised: IE80-10 Do we control station heat and demin systems
as ‘contaminated’ systems… negligible dose impact, impossible to measure activity by normal survey methods; posting requirements?
What LLDs do we need to achieve to call the system “clean”? Effluent? Environmental?
ALARA considerations… negligible dose consequences to leave as is (DWST concentration is at EPA drinking water standard); real dose is incurred to fix the “problem”
Summary Don’t overlook the obvious! Tritium can pose special concerns What other systems could have similar cross-
ties? Which LLDs does one use to declare victory
and call a IE80-10 system “clean”? How much time, effort, money, and REAL
DOSE should be expended to fix a problem that has no dose impact?