ML20210S174
| ML20210S174 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/23/1986 |
| From: | Mckenna E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210S171 | List: |
| References | |
| NUDOCS 8610080029 | |
| Download: ML20210S174 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPP-3 1.
The Nuclear Pegulatory Commission (the Commission) has found that:
A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated September 30, 1985 as revised August 22, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and and regulations s!t forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
7.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:
8610080029 860923 PDR ADOCK 05000029 P
I 7
, (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 99, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$ ]})C k a b 4 %
L Eileen M. McKenna, Project Manager Project Directorate #1 1
Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1986 9
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ATTACHMENT TO LICENSE AMENDMENT NO.99 FACILITY OPERATING LICENSF NO. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
PEMOVE INSERT 3/4 12-1 3/4 12-1 3/4 12-3 3/4 12-3 6-12 6-12 e
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3.4.12 RADIOLOGICAL EhvIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM
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LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be', conducted as'specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
I With the radiological environmental monitoring program not being a.
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 no*c 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, sdasonal 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.
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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 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
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medium, this report shall be submitted if:
concentration (1) 4 concentration (2)
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reporting level (1) reporting level (2)
When radionuclides other than those in Table 3.12-2 are detected and k
are the result of plant effluents, this report shall be submitted if the potential annual dose to a HIMBER OF THE PUBLIC is equal or 4
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 affluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
YANKEE-ROWE 3/4 12-1 Amendment No.I 3YY,99 I
8 TABLE 3.12-1 N
7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- 8 Exposure Pathway Number of Sample Sampling and Type and Frequency and/or Sample Locations Collection Frequency of Analysis 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.
Particulate sampler: Gross beta radioactivity following filter change. Composite (by location) for gamma isotopic at least once per quarter.
Y.
c 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 l[
a period of one month, analysis of each sample.
5 Tritium analysis of composite sample at least once per quarter.
U" b.
Ground 2
At least once per quarter.
Gamma isotopic and tritium
{f analyses of each sample.
@g c.
Sediment from 1
At least once per 6 months.
Gamma isotopic analysis of Shoreline each sample, u>
1 4)
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 implamenting 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 PROGAAM 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 procedyres at least once per 12 months, i 25%.
1.
Any other area of facility operation considored 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 udnutes 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.
YANKEE-ROWE 6-12 Amendment No. f6, 80, 83, 99
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