ML19225B083
| ML19225B083 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/20/1979 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19225B086 | List: |
| References | |
| JPN-79-43, NUDOCS 7907230494 | |
| Download: ML19225B083 (2) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK g
N to CcLUMeus CIRCLE NEW YORK. N. Y.10019 I
L212) 347 6200
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M5 July 20, 1979 JPN-79-43 Director, Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors
Subject:
James A.
FitzPatrick Nuclear Power riint Docket No. 50-333 Proposed Radiological Effluent and Monitoring Technical Specificaitons
Dear Sir:
In response to your letter of June 12, 1979, enclosed please find ten (10) copies of the Offsite Dose Calculation Manual (OCCM) prepared in accordance with Attachment A of the acove referenced letter.
The Power Authority does not consider this CDCM to be part of the Technical Specifications for the FitzPatrick facility.
As described in proposed Technical Specification Section 6.16 of the Authority's May 2, 1979 letter on the subject item, the ODCM shall describe the methodology and parameters to be used in the calculation of off-site doses due to radioactize gasecus and liquid effluents and in the calculation of gasecus and liquid efflaents monitoring instrumentation alarm / trip fc:
setpoi.ts consistent with the applicable Limiting Conditions Operation contained in the prcposed Technical Spec'ficaticns.
The CDCM shall be maintained at the plant and will refitet accepted methedclogies and calculational prccedures, and therefore, is only referenced in the proposed Technical Specifications.
Since the waste disposal system at the FitzPatrick faciliti already ccmplies with the regulations set forth in 10 CFR 550.34a, Appendix A Criterion 60, and Appendix I, the Authority believes that further commitments to your request of November 15, 1973 for waste sclidificaticn carnot be made a: this time.
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o The Authority believes that the requirements for the ship-ment of radicactive wastes in 10 CFR 571 c~o not require solidificat-
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In addit on, the Department of Transportation and the burial sites i
themselves do not require that waste be solilified.
The Authoriti does act agree with the NRC staff's definition of solid fication, particularly the requirement for homcgeneity.
The Authcrity celieves that, compared to the benefits achieved, the pro'ected dose levels associated with your requested solid waste suuveillance requirements are inconsistent with the ALARA program.
The Authority would also be interested in receiving a ccpy of the dccumentation.; p e n w h i c'.-
four staff concluded th t the propcsed actions in four Novemher 15, 1973
'a*"o-will provide substantial additional protection of the public health and safety as stipulated under 10 CFR J50.109.
Very tr'ilv. vours,
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Assiscant Chief Engineer-Projects f
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