ML20151X112

Corrected Page to Amend 142 of License NPF-1 Re Administrative Controls

ML20151X112
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/17/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151X110	List: ML20151X106 ML20151X112
References
NUDOCS 8808250226
Download: ML20151X112 (1)

Text

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. ADMINISTRATIVE CONTROLS (iii) Identification of the various sampling points.

(iv) Procedures for recording and management of data.

(v) Procedures defining corrective actions for off control point chemistry condition.

(vi) A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of the administrative events required to initiate corrective action.

d. Post-Accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and Containment atmosphere samples under accident conditions. The program shall include the following:

(1) Training of personnel, (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

6.8.5 Procedures for radiological environmental monitoring shall be approved and implemented in accordance with the P,GE Nuclear Quality Assurance Program.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Connission, ATTN: Document Control Desk, Washington D.C. 20555, with copies sent to the Regional Administrator, USNRC, Region V, and the USNRC Resident Inspector.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level, l3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory TROJAN-UNIT 1 6-14a Amendment No. 18, 21, 42, 97, 99, 70, 128, 142 Correction Letter dated August 17 , 1988 8803250226 880817 PDR ADOCK 05000344 P PDC

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