Tritium in The Demin Water System -- An IE Bulletin 80-10 Challenge Ken Sejkora Entergy Nuclear Northeast – Pilgrim Station Presented at the 12 th Annual.

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Presentation transcript:

Tritium in The Demin Water System -- An IE Bulletin Challenge Ken Sejkora Entergy Nuclear Northeast – Pilgrim Station Presented at the 12 th Annual RETS-REMP Workshop Atlantic City, NJ: 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 = 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

Tritium Exchange From CSTs

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 EndDWST 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?