ML20247A910
| ML20247A910 | |
| Person / Time | |
|---|---|
| Site: | Hatch  (DPR-57-A-166) |
| Issue date: | 07/18/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247A915 | List: |
| References | |
| NUDOCS 8907210348 | |
| Download: ML20247A910 (5) | |
Text
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[4' UNITED STATES
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g.g NUCLEAR REGULATORY COMMISSION g
a WASHINGTON, D. C. 20555 GEORGIA POWER COMPANY OCLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA I
CITY OF DALTON. GEORGIA
)
DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.166 License No. DPR-57 1.
The Nuclear Pegulatory Commission (the Comission) has found that:
A.
The application for amendment t'o the Edwin.I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia,(thelicensee)datedMarch 20, 1989, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by thi. amensment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complir.nce with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the pt611c; 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.
8907210348 89071e PDR ADOCK 05000321 P
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Accordingly, the license is amended by changes to the Technical Specifi-i cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No.166, 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 its date of' issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION avid B. Matthews, Director P.roject Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Teciinical Specifications Date of Issuance:
July 18, 1989 l
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2.-
Accordingy, the license is arwnded by changes to the Technical Specifi-l-
cations as indicated in the attachment to this' license amendment, and
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paragraph 2.C.(2) of Facility Operating License No. DPR-57 is' hereby J
amended to read as follows:
j
~(2) Technical' Specifications The Technical Specifications contained. in Appendices A and B, as revised through Amendment No.- 166, are hereby incorporated.in the license. The licensee shall operate the facility in accordance with
' the Technical-Specifications.
3.
This license anendnent is effective as of its date of issuance and shall be imp'lemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. Origic Signed By:
Dwid B. Matthews David D. Matthews, Director Project Directorate 11-3
' Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of.-Issuance:
July 18, 1989 0FFICIAL RECORD C0P ',
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ATTACHMENT' TO' LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. DPR-57
,f DOCKET NO. 50-321 -
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.- The revised oage is ' identified by amendment number and J
contains a vertical line indicating the area of change.
)
Remove Page Insert Page 1
3.6-6 3.6-6 I
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- c i1RITIM renITION5 FOR OPEEaTION 5MVEII_n amrg agguIntsummT5 3.6.F.2.h Condu$tivitv " Chloride 4,6.r.2.
Conductivity and Chlorid, a.
During reactor operation when the 4.
Reactor coolant shall be reactor is pressurized, or above continuously monitored for b
212'F, and at less than 15 of conductivity.
rated steam flow,- including hot J
standby, the reactor coolant (1) Whenever the continuous shall not exceed the following conductivity monitor is <
. limits:
inoperable, an inline conductivity measurement Conductivity - Sumho/cm at shall be obtained:
.25*C Chloride
- 0.1 ppe (a) At least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when the b.
During reactor operation in excess
' reactor coolant of 15 of rated steam flow, the-temperature is reactor coolant shall not exceed
>212' F.
the following limits:
(b). At least once every Conductivity - 2pmho/cm at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the 25'c reactor coolant Chloride
- 0.2 ppm temperature is
$212* F.
c.
The reactor coolant may exceed the limits of Paragraphs a and D, oniy (2) Once a week the contin-for the time limits specified here.
uous conductivity monitor Exceeding these time limits or the shall be checked with an following maximum limits shall be inline flow cell. This cause for immediately shutting inline conductivity cal-down and placing the reactor in*
ibration shall be per-the cold shutdown condition, formed every 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-whenever the reactor Conductivity - Time above the coolant conductivity is-conductivity
>2.0 waho/cm at 25'C.
limits in para-graphs a and b b.
During startup prior. to at 25'C, 2 pressurizing the reactor weeks / year, above atmospheric pressure, Maximum limit -
measurements shall be 10 waho/cm performed to show conformance at 25'C.
with section a. of limiting conditions.
- Time above 0.2 ppm 2 weeks /
c.
Whenever the reactor is oper-year. Maximum ating (including hot standby limit - 0.5 ppm.
conditions), measurements of-reactor water quality shall The reactor shall be shut down if.
be performed according to pH is <5.2 or >9.0 for a 24-hour the following schedule:
period.
(1) Chloride ion content d.
When the reactor is not pressur-shall be measured at ired (i.e., at or below 212'F),
least ori;e every 96 reactor coolant shall be hours.
maintained below the following limits:
(2) ChlorMe ion content shall be measured at Conductivity - 10 umho/cm leas't o*ce every B hours at 25'C whenevs' reactor coolant Chloride
- 0.5 ppm conductivity is >2.0 umho/ cm at 25'C.
cad pH th*11 te t'etween 5.') and 8.6.
m
>w i 166 Amendment No. 166
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