ML20033B712
| ML20033B712 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/27/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033B668 | List: |
| References | |
| NUDOCS 8112010661 | |
| Download: ML20033B712 (3) | |
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.,r SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPANSION OF QUAD CITIES STATION UNITS 1 & 2 SPENT FUEL'POO STORAGE
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. DOCKET NO. 50 - 254/2b5 SPENT FUEL POOL CLEANUP SYSTEM s
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INTRODUCTION The spent fuel pool cleanup system consists of a filter demineralizer (precoat filter material and powdered anion.and cation resin), filters, and associated piping, valves, and fittings.
The
. system is designed to remove corrosion products, fission products, and impurities from the pool water.
Pool water purity is monitored inlet to the by a continuous conductivity metdr installed on the fuel pool demineralizers,' and by periodic grab samples for laboratory analysis.
Once a week a representative grab sample is for obtaineo from the fuel pool demineralizer inlet line for p i
chloride, silica, and turbidity a'nalysis.
Weekly activity checks are made f or gr oss beta and gross alpha.
Once a month a sample from the same location is obtained for a gamma isotopic analysis.
All peaks are identified.
All identified isotopes are quantifiedi and an.LLD is determtned for,K -85.
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r The criterion for a demineralizer backwash and precoat is a consistent excursion from the chemistry. Limits, or high ditferential pressure (25 psid) across the deminer'alizer.
We Egree with the Licensee that the proposed high density fuel storage will not alter 'the chemistry or radiochemistry of the spent fuel pool water.
8112010661 811127 PDR ADOCK 05000254 G
PDR'
e II.
EVALUATION Past experience showed that the greatest increase in radioactivity and impurities in spent fuel pool water occurs during refueling and spent. fuel handling.
The refueling frequency, the amount of core to be replaced for each fuel cycle, and frequency of operating the spent fuel pool cleanup lystem are.not expected to increase as a result of high density fuel storage.
The chemical and radionuclide composition of the spent fuel pool water is not expected to change as a result of the proposed high density fuel storage.
Past experience also shows n'o significant. Leakage of fission products from spent fuel stored in pools occurs after the fuel has cooled for several months.
To maintain water quality, the Li c en s e e ha s e st ab lj she'd th e f r'e quency o~f chemi c'a t and radionucLide analysis that w1LL be performed to monitor the
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water quality and the need for spent fuel pool cleanup system re'lacement.
In addition, the demineralizer resin and filter p
Licensee has also set the chemical and radioch.emical limits to be used in monitoring the spent fuel pool water quality and initiating corrective action.
We agree with the Licensce's contentionsi that the increased quantity of spent fuel to be stored wilL not contribate s,ignificantly to the amount of radioactivity from fission products in the spent fuel p'ool water.
We conclude tha,t the proposed expansion of the spent fuel pool WilL not appreciably affect the capability and capacity of the existing spent fuel pool cleanup system.
More frequent replacements of filters or demineralizer resin, required when G
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the differential pressure exceeds 25 psid or decontamination effectiveness is reduced as indicated by the Licensee, can offset any potential increase in radioactivity and impurities in the poal water as a result of.theexpansionofs(oredspent fuel.
Thus we have determined that the existing fuel pool cleanup syst'em with the proposed 1.igh density fuct storage (1) provides the-capability and capacity of removing radioactive materials, corrosion products, and impurities from the pool and thus meets the requirements of General' Design Criterion 61 in Appendix A of 10 CFR P, art 50 as it relates to appropriate systems to fuel storage; (2) is capable of
. reducing occupational exposures to radiation by removing, radioactive products from the popt water, and thus meet the requirements of Section 20.1(c) 'of 10 CFR Part 20, as-it relates to maintaining radiation exposures as low as is reasonably achievable; (3) confines radioactive materials in the pool water into the filters and demineralizers, and thus meets Regulatory Position C.2.f(c) of Regulatory Guide 8.8, as it relates to reducing the spread of contaminants from the source; and'(4) removes :ucpended impurities from pool water by filters, and thus meets Regulatory Position C.2f(3) of P
8egulatory Guide 8.8, as'it relates to removing crud from fluids thr'ough physical action.
CONCLUSION On the basis of the above evaluation, we conclude th,at the fuel pool cleanup system meets GDC6'1r Section existing spent 20.1(c) of 10 CFR Part 20 and the appropriate Sections of
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Regulato,ry Guide 8.8 and, therefore, is acceptable for the proposed high density fuel storage.
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