ML20071Q202
| ML20071Q202 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/08/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071Q204 | List: |
| References | |
| NUDOCS 9408110125 | |
| Download: ML20071Q202 (7) | |
Text
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o UNITED STATES 3'
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE q
Ar.;cadment No.134 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated July 19, 1994, as supplemented August 4, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations as 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 Comnission; 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 set forth l
in 10 CFR Chapter I; 1
l 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 l
been satisfied.
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9408110125 940800 hDR ADOCK 05000366 PDR l
l1 l 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION 1
f 4
4 Her ert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
1 Technical Specification I
Changes j
Date of Issuance:
August 8, 1994 I
l
P ATTACHMENT TO LICENSE AMENDMENT NO.134 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 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.
Remove Paaes Insert Paaes 3/4 3-57 3/4 3-57 3/4 3-57a 3/4 3-57b B 3/4 3-4 B 3/4 3-4
INSTRUMENTATION TRAVERSING INCORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.6.6 The traversing incore probe system shall be OPERAB'.E with:
Four movable detectors, drives, and readout equipment to map the l
a.
core, and b.
Indexing equipment to allow all required detectors to be normalized in ]
4 common location.
APPLICABILITY:
When the traversing incore probe is used for:
a.
Recalibration of the LPRM detectors and b.
Monitoring the APLHGR, LHGR, or MCPR.
AC. TION:
I a.
With one or more TIP rreasurement locations inoperable, required measurements may be performed as described in 1 or 2 below.*
1.
TIP data for an inoperable measurement location may be replaced by data obtained from that string's radundant (sym etric) counterpart if the substitute TIP data were obtained from an operable measurement location and the control rod pattern is octant rymetric, provided the total TIP uncertainty for the present cycle has been measured to be less than 8.7 percent.
2.
TIP data for an inoperable measurement location may be replaced by data cbtained from the on-line core monitoring system (process computer) normalized with available operating measurements, provided the total number of simulated channels (measurement locations) does not exceed eight.
b.
Otherwise, with the TIP system inoperable, do not use the system for the above appilcable monitoring or calibration functions for more than 31 EFPD following the last normalization.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
- Action a is applicable until the end of Cycle 12.
HATCH - UNIT 2 3/43-57 Amendment No. 134 l
INSTRUMENTATION TRAVERSING INCORE PROBE SYSTEM LIMITIf!G CONDITION FOR DPERATION SURVEILLANCE RE0VIREMENTS l
l 4.3.6.6 The traversing incore probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs prior to or during use when required for the above applicable monitoring or calibration functions, if not performed within the previous 31 EFPD.
HATCH - UNIT 2 3/4 3-57a Amendment No.134 l
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(This page intentionally left blank.)
l HATCH - UNIT 2 3/4 3-57b Amendment No. 134
1 INSTRUMENTATION BASES HONITORING INSTRUMENTATION (Continued) 3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant param-eters to monitor and assess important variable following an accident.
3/4.3.6.5 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during startup.
At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM The OPERABILITY of the traversing incore probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution in the reactor core.
The specification allows use of substituted TIP data from symmetric channels, adjusted by the plant computer to remove machine and power level dependent biases, if the control rod pattern is symmetric. The source of substituted data may also be calculations performed by the on-line computer core monitoring system which are normalized to available real data.
Symmetry is not required for substitution of calculated readings.
3/4.3.6.7 MCRECS ACTUATION INSTRUMENTATION The OPERABILITY of the MCRECS ensures the necessary protective actions will be automatically initiated to provide protection for control room personnel.
3/4.3.6.8 (Deleted)
HATCH - UNIT 2 B 3/4 3-4 Amendment No. 134 l