ML20133C580

Proposed Tech Specs Re Radiological Environ Monitoring

ML20133C580
Person / Time
Site:	Yankee Rowe
Issue date:	09/30/1985
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20133C572	List: ML20133C569 ML20133C580
References
NUDOCS 8510070433
Download: ML20133C580 (4)

Text

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3.4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 5

3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimen are unobtainable due to hazardous conditions, seasonal unavailability or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling media at one or more of the locations specified in Table 3.12-1 exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days from the receipt of the Laboratory Analyses, pursuant to l

Specification 6.9.6, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 3.12-2 to be exceeded. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

i concentration (1) concentration (2)

+.. 1 1.0 reporting level (1) reporting level (2)

When readlonuclides other than those in Table 3.12-2 are detected l

and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental l

Operating Report.

AmendmentNo.p4I YANKEE-ROWE 3/4 12-1

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TABLE 3.12-1 a

7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• Exposure Pathway Number of Sample Sampling and Type and Frequency and/or Sample Locations Collection Frequency of Analysis i

1.

AIRBORNE a.

Radiolodine and 5

Continuous operation of sampler Radiolodine canister. Analyze Particulates with sample collection as required weekly for I-131.

by dust loading but at least once per week.

I Particulate sampler: Gross beta radioactivity following filter change. Composite (by location) for gamma isotopic at least I

once per quarter.

Y s~

i 2.

DIRECT RADIATION a) 22 Quarterly Gamma dose, at least once per 7

quarter.

w b) 16 Quarterly Incident response TLD;s in the outer (4-5 mile) ring, de-dose only quarterly unless gaseous release LCO was exceeded in period.

3.

WATERBORNE a.

Surface 2

Composite *** sample collected over Gross beta, gamma isotopic

{

a period of one month, analysis of each sample.

Tritium analysis of composite a

sample at least once per quarter.

b.

Ground 2

At least once per quarter.

Gamma isotopic and tritium z

analyses of each sample.

o 2

k 2(

c.

Sediment from 1

At least once per 6 months.

Gamma isotopic analysis of j

Shoreline r

each sample, v

I

1 1

ADMINISTRATIVE CONTROLS f.

The Facility Security Plan and implementing procedures at least once per 12 months, i 25%.

g.

The Facility Fire Protection Program and implementing procedures at least once per 24 months, i 25%.

h.

The radiological environmental monitoring program and the results thereof at least once per 12 months, i 25%.

i.

The Off-site Dose Calculation Manual and implementing procedures at least once per 24 months, i 25%.

J.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive waste at least once per 24 months, i 25%.

k.

The performance of activities affecting quality as required by effluent and environmental monitoring procedures at least once per 12 months, i 25%.

1.

Any other area of facility operation considered appropriate by the NSAR Committee or the Vice President.

AUTHORITY 6.5.2.10 The NSAR Committee shall report to and advise the Vice President on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9.

RECORDS 6.5.2.11 Minutes of each NSAR Committee meeting shall be prepared and forwarded to the Vice President and each member of the Committee for review within 20 working days following each meeting. The meeting minutes shall include, where applicable, reports of reviews encompassed by Section 6.5.2.8; and reports of audits encompassed by Section 6.5.2.9.

The review of the minutes shall be completed within 60 days of the date of their distribution.

6.5.3 INDEPENDENT AUDIT AND REVIEW 6.5.3.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.

AmendmentNo.pd,jPI YANKEE-ROWE 6-12

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ADMINISTRATIVE CONTROLS 6.5.3.2 An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24-hour notification to the Commission shall be reviewed by the PORC and submitted to the NSAR 3

Committee and the Manager of Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety Limit is i

violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour.

b.

The Safety Limit violation shall be reported to the Commission, the Manager of Operations and to the NSAR Committee within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Plant Operation Review Committee. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action-taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the NSAR Committee and the Manager of Operations within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained that meet or exceed the requirments and recommendations of Sections 5.2-5.2.9 and 5.3 of ANSI N18.7-1976 and Appendix "A" of Regulatory culde 1.33, Reivsion 2, except as provided in 6.8.2 and 6.8.3 below. The written procedures shall also cover the activities relating to:

a.

FIRE PROTECTION PROGRAM implementation.

b.

PROCESS CONTROL PROCRAM implementation.

c.

OFF-SITE DOSE CALCULATION MANUAL implementation.

d.

Quality assurance for effluent and environmental monitoring.

YANKEE-ROWE 6-13 Amendment No.

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