ML19249E402
| ML19249E402 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/29/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19249E403 | List: |
| References | |
| NUDOCS 7910010319 | |
| Download: ML19249E402 (5) | |
Text
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UNITED STATES t
NUCLEAR REGULATORY COMMISSION
[Y]W/
I W ASHINGTON, D. C. 20666 X. j GEORGIA POWER COMPANY OGLETHORPE ELECTRIC MEMBERSHIP CORPOPATION MUNICIPAL ELECTRIC ASSOCIATION OF GEORGIA I
99i D
CITY OF DALTON, GEORGIA gg O
h DOCKET NO. 50-321 9' O u (0] d iJ I
EDl:IN I. HATCH NUCLEAR PLANT UNIT NO. 1 v
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.
(the licensee) dated July 13, 1979, complies with the standards ar.d requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 avid regulations of the Commission; 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 Commission's regulations; D.
The issuance of this amendment will i.;t be inimical to tre 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.
7910 010 J /f 12:5_154
. 2.
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. OPR-57 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, 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 RESULATORY COMMISSION A
o, Chief Operating Reactors Branch d3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 29, 1979
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J ATTACHMENT TO LICENSE AMENDMENT N0. 71 FACILITY OPERATING LICENSE N0. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment rumber and contain vertical lines indicating the area of change.
Remove Insert 3.6-9 3.6-9 3.6-9a 9
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V
O LIMITING CO'iDITIONS FOR OPERATION SURVEILLANCT 'kEQUIPIMENTS 3.6.H.
Relief /Safetv Valves 4.6.H.
Relief /Safetv Valves 1.
When more than cce relief / safety 1.
End of Ocerating Cvele valve is known to be failed an orderly shutdown shall be. initiated Approximately one-half of all and the reactor depressurized to relief / safety valves shall be less than 113 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
benchchecked or replaced with Frior to reactor startup from a a benchchecked valve each re -
cold condition all relief / safety fueling cutage. All 11 valves valves shall be operable.
will have been checked or replaced upon the completion of every second operating cycle.
- 2. With one or more relief / safety
- 2. Each Ooeratina Cvele valve (s) stuck open, place the reactor mode switch in the shutdown position.
Once during each operating cycle, at a reactor pressure
>100 psig each relief valve shall be manually opened until ther=occuples downstream of the valve indicate steam is flowing from the valve.
- 3. With one or more relief / safety
- 3. Integrity of Relief Valve Bellows
- valve tail pipe pressure switches inoperable and the associated The integrity of the relief valve relief / safety valve (s) otherwise bellows shall be continuously indicated to be open, place the monitored and the pressure switch reactor mode switch in the shutdown calibrated once per operating cycle position.
and the ~ accu =ulators and air piping shall be inspected for leakage once per operating cycle.
4.
Relief Valve Maintenance At least one relief valve shall be disassembled and inspected each operating cycle.
- 5. Operability of Tail Pipe Pressure Switches The tail pipe pressure switch of each relief / safety valve shall be demonstrated operable by perfor=ance of a:
a.
Functional Test:
I i
1.
At least once per 31 days, except that all portiens of instru=entation inside the pri=ary containnent
=ay be excluded from the
=:ces not apply to two-stage Target Rock SRVs functional test, and Amendment flo. 36, 71 3.6-9
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.6.H.
Relief / Safety Valves (Continued) 5.
Operability of Tail Pipe Pressure Switches a.
Functional Test:
- 2. At each scheduled outage greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> riuring which entry is made in:o the primary containment, if not performed within the previous-31 days.
b.
Calibration and verifying the setpoint to be 20 j-5 psig at least once per 18 conths.
.I.
Jet Pu=os I. Jet Pu=es Whenever the reactor is in the Whenever both recirculating pumps Start & Hot Standby or Run Mode are operating with the reactor in with both recirculating pumps the Start & Hot Standby or Run Ibde, operating, all jet pumps shall be jet pump operability shall be checked operable.
If it is determined that daily by verifying that the following a fet pu=p is inoperable, an orderly conditions do not occur simultaneously.
shutdown shall be initiated and the reactor shall be in the Cold Shut-
- 1. The two recirculation loops have down Condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a flow imbalance of 15% or = ore when the pumps are operated at the sa=e speed.
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Jrg Amendment No. 71 3.6-9a