ML19330C160
| ML19330C160 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/28/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19330C161 | List: |
| References | |
| NUDOCS 8008080022 | |
| Download: ML19330C160 (5) | |
Text
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g NUCLEAR REGULATORY COMMISSION wAsmucTom. o.c.2osss GEORG POWER COMPANY OGLETHF#* 90WEP CORPORATION MUNICTFAF 'ift iTC AUTHORITY OF GEORGIA CITTN DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE, Amendment No. 77 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated July 2,1980, complies with the standards and 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 and regulations of the Comission; C.
There is reasonable assurance (il 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; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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. DPR-57 is hereby amended to read as follows:
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 77
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FACILITY OPERATING LICENSE NO. DPR-57 1!
DOCKET NO.'50-321 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
r Remove Insert
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3.5-7 3.5-7 3.5-8*
3.5-8*
- 0verleaf; no changes on th.is page.
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.5.D.1, Normal Operational Tests (Continued)
The HPCI-pumps shall deliver 3.5.D.2. ' Operation with Inoperable at least 4250 gpm during each Components flow rate test.
If the HPCI system is inoperable,
- c. Pump Oper-Once/ month j
the reactor may remain in oper-ability l
ation for a period not to' exceed l
fourteen (14)' days provided the ADS,
- c. Mot r Oper-Once/ month CS system, RHR system LPCI rode, ated valve and RCIC system are operable, operability 2.
Surveillance with Inoperable Components With the surveillance requirements of Specification 4.5.D.1 not per-formed at the required frequencies When the HPCI system is inoper-able, the ADS actuation logic, due to low reactor steam pressure, the RCIC system, the RHR system reactor startup is. permitted and LPCI mode, and the CS system the appropriate surveillance will shall be demonstrated to be oper-be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after able immediately. The RCIC ' system reactor steam pressure is adequate and ADS logic shall be demon-to perform'the tests.
strated to be operable daily thereaf ter until the HPCI system is returned to normal operation.
i 3.
Shutdown Requirements If Specification 3.5.D.1 or 3.5.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor vessel pressure shall be reduced to 113 psig or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Reactor Core Isolation Cooling E.
Re5ctor Core Isolation Cooling (RCIC) System (RCIC) System
- 1. Normal System Availability
- 1. Normal Operational Tests RCIC system testing shall be performed as follows:
Item Frequency
- a. The ~ RCIC System shall be operable:
- a. Simulated Once/ Operating Automated Cycle
.(1) Prior to reactor startup -
Actuation from a cold condition, or Test i
Amendment No. 77 3.5-7
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b LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIFJMENTS s
'3.5.E.1.
. Normal System Availability (Continued) 4.5.E.1.
Normal Operational Tests (Continued) a.(2) when there is irradiated fuel.in the reactor vessel and the reactor pressure is above 113 psig, except
'as stated'in Specification 3.5.E.2.
Item Frequency
- b. Flow' rate at once/3 months normal reactor vessel oper-ating pressure and Flow rate at Once/ Operating 150 psig cycle reactor pressure The RCIC pump shall deliver at least 400 gpm during each flow test.
- c. Pump Oper-Once/ month ability
- d. Motor Oper-Once/ month ated valve operability 2.
Surveillance with Inoperable 2.
Operation with Inoperable Componenes Components-If the RCIC system is inoperable, When the RCIC system is inoper-the reactor may remain in oper-able,. the HPCI system shall be ation for a period not to exceed demonstrated to be operable seven' (7) days if the HPCI system immediately and daily thereafter until the RCIC system is returned is operable during such time, to normal operation 3.
Shutdown Requirements' If Specification 3.5.E.1 or 3.5.E.2 is not met, an orderly shutdown shall be initiated and the reactor shall be depressurized
[
- to lass than 113 psig within '
I 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5-8
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