ML20052F740
| ML20052F740 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/06/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F739 | List: |
| References | |
| NUDOCS 8205130548 | |
| Download: ML20052F740 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. NPF-1 1.
The Nuclear Regulatory Comissio:1 (the Comission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated April 12, 1982 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 ass'urance (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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon
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defense and security or to the health and safety of the public; and
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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.
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8205130548 820506 PDR ADOCK 05000344 P
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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. NPF-1 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall opetate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1982 r
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ATTACHMENT TO LICENSE XMENDMENT AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-37 3/4 3-37 B 3/4 3-2 B 3/4 3-2 1
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INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:
a.
At least 757, of the detector thimbles for Applicability B','
6 and 0, b.
At least 18 thimbles for quarter-core flux maps for Applicability A, c.
A minimum of 2 detector thimbles per core quadrant for Applicability B, C and D, and I
d.
lufficient movable detectors, drive, and readout equipment to map these thimbles.
APPLICABILITY:
When the movable incore detection system is used for:
1 A.
Recalibration of the axial flux offset detection system (QUADRANT POWER TILT RATIO less than or equal to 1.02),
B.
Re;alibration of the axial flux offset detection system (QUADRANT POWER TILT RATIO greater than 1.02),
C.
Monitoring the QUADRANT POWER TILT RATIO, or D.
Measurement of F and Fg (Z).
H ACTION:
I With the movable incore detection system inoperable, do not use the system t
l for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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l SURVEILLANCE REQUIREMENTS
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4.3.3.2 The incore movable detection system shall be demonstrated OPERABLE by nomalizing each detector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to l(
its use when required for:
I ll a.
Recalibration of the excore axial flux offset detection system, l
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Monitoring the QUADRANT POWER TILT RATIO, or c.
Measurement of F and Fg (Z).
H l?.1 T:10JAN-UNIT 1 3/4 3-37 korun: 10. 72
INSTRUMENTATION RASES RADIATION MONITORING INSTRUMENTATION (Continued) by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of eouioment ensures that the measurements obtained from use of this system accurately represent the saatial neutron flux ~
distribution of the reactor core.
For the purpose of measuring F (Z) or F H, a full incore flux map g
is used. Quarter-core flux macs, as defined in WCAP-8648-A (February 1979) may be used in recalibration of the excore axial flux offset detection'sy'ATIO st'em provided that reasonable radial symmetry exists (QUADRANT POWER TILT R less than or equal to 1.02).
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufff-cient capability is available to promotly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is reouired to permit comparison of the measured response to that used in the design basis for the facility and is con-sistent with the recommendations of Regulatory' Guide 1.12, " Instrumentation for Earthcuakes."
3/4.3.3.4 METEOROLOGICALINSTRUSENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the oublic as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating orotective measures
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to protect the health and safety of the oublic. and is consistent with the recommendat,1,ons of Regulatory Guide 1.23, "0nsite Meteorological Programs."
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION r
The OPERARILITY of the remote shutdown instrumentation ensures that sufficient cacability is available to permit shutdown and main-tenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is reouired in the event control room habitability is lost and is consistent with General Design Criteria 19,of 10 CFR 50.
TROJAN-UNIT 1 B 3/4 3-2 Amendment No. 72
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