ML20151Q541
| ML20151Q541 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/03/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20151Q544 | List: |
| References | |
| NPF-68-A-008 NUDOCS 8808110203 | |
| Download: ML20151Q541 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20655
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATIriG PLANT, UNIT 1 AMENDfiENT TO FACILITY OPERATING LICENSE Amendment No.
8 License No. NPF-68 1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for atirandment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Scility Operating License No. NPF-68 filed by the Georgia Power Company acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Calton, Georgia, (the licensees) dated February 4, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license 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 i
of the Comission's regulations and all applicable requirements have been satisfied.
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, 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment dnd parugrdph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to redd as follows:
(2) _ Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, os revised through Amendment No.
8, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmentol Protection Plan.
3.
This license amendment is effective as of its ddte of issuance and shdll be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COPHISSION Original Signed By:
David B. Matthews, Director Project Directorate II-3 Division of Redctor Projects
Attachment:
Technical Specification Chdnges Date of Issudnce: August 3, 1988 0FFICIAL RECORD COPY 7
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ATTACHMENT TO LICENSE AMEhDMENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Amended Page Overleaf Page 3/4 3-66 3/4 3-65 3/4 3-68 3/4 3-67
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The Alarm /
Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-9.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.8.1.4 why this inoperability was not corrected in a timely manner.
The provisions of Specifications 3.0.3 and 3.0.4, are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-5.
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V0GTLE - UNIT 1 3/4 3-65
TABLE 3.3-9 y
8p RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION m
i i
E MINIMUM Z
CHANNELS INSTRUMENT OPERABLE ACTION y
1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluent Line (RE-0018) 1 37 b.
Steam Generator Blowdown Effluent Line (RE-0021) 1 38 c.
Turbine Building (Floor Drains) Sumps Effluent Line (RE-0848) 1 38 I
2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Nuclear Service Cooling Water System Effluent Line (RE-0020 A & B) 1 39 I
3.
Flow Rate Measurement Devices i
a.
Liquid Radwaste Effluent Line (FT-0018) 1 40 1
b.
Stean: Generator Blowdown Effluent Line (FT-0021) 1 40 c.
Flow to Blowdown Sump (AFQI-7620, FR-7620, pen 1) 1 40 P
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E
l TABLE 3.3-9 (Continued)
ACTION STATEMENTS ACTION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 10 7 microcurie /ml:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
ACTION 39 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radio-activity at a lower limit of detection of no more than 10 7 microcurie /ml.
ACTION 40 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated
)
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump per-i formance curves generated in place may be used to estimate flow.
1 V0GTLE - UNIT 1 3/4 3-67 l
TABLE 4.3-3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS c
AF'ALOG 35 CHANNEL i
-d CHANNEL SOURCE CHANNEL OPERATIONAL l
INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluant Line (RE-0018)
O P
R(3)
Q(1) b.
Steam Generator Blowdown Effluent Line (RE-0021)
D M
R(3)
Q(1)
R c.
Turbine Building (Floor Drains) Sumps j'
Effluent Line (RE-0848)
D M
R(3)
Q(1) l 03 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release Nuclear Service Cooling Water System Effluent Line (RE-0020 A & B)
D M
R(3)
Q(2)
E 2e
.