ML19329A281
| ML19329A281 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/09/1977 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001020853 | |
| Download: ML19329A281 (5) | |
Text
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[ bl DEC 0 91977 Docket Hos.: 50-267/270/287 MEtORANDUM FOR:
B. K. Grimes, Chief I
Envimnmental Evaluation Branch Division of Operating Reactors I
FROM:
J. T. Collins, Chief Effluent Treatment Systems Branch l
Division of Site Safety and
~
Environmental Analysis
SUBJECT:
CCONEE NUCLEAR STATION, UNIT NOS.1, 2 AND 3. - TECHNICAL i
I SPECIFICATION CHAf1GE TO CONTROL SECONDARY COOLANT TREATMENT RELEASES
. We have reviewed the memorandum, dated November 17, 1977, reconnending i
amendments to the Environmental sechnical Specifications for the Oconee Nuclear Station Unit Nos. 1, 2, and 3.
We concur with the revisions to the specifications that you recommend.
In addition, we suggest several changes to implement 10 CFR Part 50, Appendix A General Design Crit 6rta 60 relative to the control of secondary system effluents and the ETSB proposed revision to SRP 11.5.
Enclosed are our consents.
j CRIGINAL SIGNED S'l DISTRIBUTION:
,1* T. c0LLIUS '
DOCKET FILES 50-267/270/287
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DSS READING John T. Collins, Chief ETSB READING Effluent Treatment Systems Branch JTCOLLINS Division ( ~ Site Safety and Environmental Analysis Enclosum:
ETSB Comments cc:
D. Eisenhut K. Goller R. Vollmer L. Barrett W. Burke R. Bangart J. Lee J. Boegli l
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i COMMENTS ON THE 'R0 POSED TECHNICAL SPECIFICATION AMENDMENT FOR OCONEE NUCLEAR STATION, UNIT N05. 1, 2, AND 3 (DocketNos.
50-267/270/287) 1.
Requirement for Turbine Building Sump Monitor, Item 1 The secondary system condensate filter /demineralizers automatically discharge to the turbine building sump. Units 1 and 2 share a sump,' art the inlet is to be monitored with an alarm to the control room. Unit 3'is independent and the inlet is to be monitored with-an alarm to the control room.
These sump inlet monitors do nor provide automatic isolation of turbine building sump releases and must rely on batch release administrative control (see item 3, below); therefore, they are process monitors. Their alarm set point (not g'iven) provides administrative control for diverting filter /demineralizer waste resins and liquid to the radioactive solids systems by manual control. Therefore, any radioactive resin or liquid in the waste water collection basins is a failure of administrative controls, malfunction of the monitors, or
. inadequate sensitivity of the monitors.
COMMENT Consider adding the set point on the turbine building inlet monitors to alarm at (S x 10-6) uCi/ml liquid and (10-4) uCi/ gram resin gross beta-gamma radioactivity. Consider adding the requirement that the filter /demineralizer resins and liquid shall be diverted d
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. to the radioactive solids system whenever the turbine building sump inlet monitors alarm or are inoperable.
Consider adding a requirement to calibrate the inonitors at least every 18 months and to perform a functional test daily.
2.
Requirement for Composite Water Sampler, Iten_2 The memorandum, dated November 17,1977, to D0R (K. Goller) indi-cates in paragraph 2, page 2, line 9, that " monthly strontium analysis is needed;" howe er, the memorandum revision item 2) and 5
the safety evaluation specify quarterly stront, m analysis. The applicant, Duke Power Company, requested in their letter of October 14,
)
1977, to consider monthly strontiue analysis at the effluent I
composite sampler in the event of radioactive liquid release to the oil collection basin (prior to the sampler). The licensee may obtain more frequent analysis at any time using the weekly or monthly composite samples; however, the technical specifications should require at least a quarterly composite sample to be analyzed quarterly for Sr-89 and '
30.
COMMENT Consider changing item 2) to require both a quarterly representa-tive sample collection frequency and a quarterly Sr-89 and Sr-90 analysis frequency.
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Requirement for Valve Alionment Checks, Item 3 The waste water collection basins must be operated on a batch basis since the downstream effluent radiation sampler monitor does not provide automatic isolation control to meet the require-ments of GCC 60.
Batch releases require that the outlet valve on each basin be closed whenever an inlet valve is open and that the outlet valve remain closed whenever the inlet valve is closed during sampling, analysis, and cleaning of the basin.
COMMENTS Consider changing the valve alignment to a description of batch release control. The basin valve numbers are needed to describe I
the operation.
Consider adding to the basin operation, the requirement for representative sampling of all resin and liquid in each batch prior to release.
4.
General Comments We agree that a representative sampler must be installed on the effluent stream to meet the requirements of GDC 64.
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proposed location, on the oil collection basins discharge, meets this requirement.
Representative liquid samplers are described in SRP 11.5 (Rev. 1).
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'Although we believe that the Oconee's filter /demineralizer treat-ment system can be made to comply with 10 CFR Part 50, ~ Appendix A, for potentially radioactive effluent monitoring and control, we believe that phase separation is a better alternative.
Duke Power Company has been approached on this question in the review
- of Cherokee, Perkins, Catawba, and McGuire -Nuclear Power Plants when they proposed adding condensate filter /demineralizers to
'i the~ secondary system.
We considered this design modification 4
in our revision to SRP.11.5 (draft), and have incorporated changes to the. Standard Technical Specifications to specifically include these potentially radioactive' effluents as was the
-t intent in Regulatory Guide'1.21, and the present Technical Speci-fications for Oconee, Unit Nos.1, 2, and 3.
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