ML20206P274

Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept & Review of Operations Committee Responsibilities

ML20206P274
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/26/1986
From:	LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20206P250	List: ML20206P261 ML20206P274 SNRC-1258, Forwards License Change Application 4 to License NPF-36, Correcting Error in Listing of Types of Radwaste Shipping Containers & Solidification Agents & Clarifying Review of Operations Committee Responsibilities.Fee Paid
References
NUDOCS 8607020064
Download: ML20206P274 (3)

Text

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ATTACH!'ENT I ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

(Figure 5.1.3-1) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determing the gaseous pathway doses. The assessment of radiation doses shall be performed in cccordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

4 The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Semiannual Radioactive Effluents Release Reports shall include the following information for each type of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report periodt j a. Container volume.

b. Total curie quantity (specify whether determi:nd by i measurement or estimate),

! c. Principal radionuclides (specify whether determined by measurement or estimate),

l d. Source of waste and processing employed (e.g., dewatered i spent resin, compacted dry waste, evaporator bottoms),

i e. Type or container (e.g., LSA box, HIC, steel liner, 55 gallon drum), and

f. Solidification agent (e.g., cement, bitumen, Dow media).

The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to '

UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculatiens and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

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ATTACHMENT II ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The ROC shall be responsible for:

a. Review of (1) all proposed procedures required by Specification 6.8 and changes thereto, (2) all proposed programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; i b. Review of all proposed tests and Experiments that affect nuclear safety; l

c. Review of all proposed changes to Appendix A Technical Specifications; l d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; ,

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e. Investigation of all violations of the Technical

Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent

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! recurrence, to the Vice President-Nuclear Operations and to the Nuclear Review Board; ,

l f. Review of all REPORTABLE EVENTS; i g. Review of station operations to detect potential hazards to j nuclear safety;

h. Performance of special reviews, investigations, or analyses l and reports thereon as requested by the Plant Manager or

! the Nuclear Review Board; i

1. Review of the Security Plan and implementing procedures and submittal of recommended changes to the Nuclear Review l

Board; I

j. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Nuclear Review I Board;

k. Review of the proposed changes to the Process Control Program (PCP); ,

1. Review of the proposed changes to the Offsite Dose Calculation Manual (ODCM);

m. Review of the proposed Major Changes to Radioactive Waste i Systems;

n. Review of Personnel Radiation Records annually to determine

how exposures mighted be lowered consistent with ALARA

principles. Document such considerations; and i

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o. Review of any accidental, unplanned, cr uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice PresidentNuclear Operations and to the Nuclear Review Board.

6.5.1.7 The ROC shall:

a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a. through d. and m. prior to their implementation. l

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a.

through e. above constitutes an unreviewed safety question.

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