ML20205E929
| ML20205E929 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/25/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20205E934 | List: |
| References | |
| NUDOCS 8703310048 | |
| Download: ML20205E929 (2) | |
Text
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y ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.
Feedwater leakage control system.
7.
Post-accident sampling system.
8.
Suppression pool level detection portion of the suppression pool makeup system.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions..This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
c.
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, 2.
Procedures for sampling and analysis, 3.
Provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS j
6.9.1 In addition to the applicable reporting requirements of Title 10, Code j
of Federal Regulations, the following reports shall be submitted to the i
Regional Administrator of the Regional Office, unless otherwise noted.
STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, therical, or, hydraulic performance of the unit.
8703310048 870325 PDR ADOCK 05000416 P
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GPAND GU'.e-UNIT 1 6-15 N.-.. -.-
ADMINISTRATIVE CONTROLS i,
STARTUP REPORTS (Continued) 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 compari-son of these values with design predictions and specifications. Any correc-tive actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events, i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation, supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTSM 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year fol-lowing initial criticality.
6.9.1.5.1 Reports shall include a tabulation on an annual basis of the number l l
of station, utility, and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated manrem exposure ac-f cording to work and job functions,M e.g., reactor operations and surveil-lance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
6.9.1.5.2 Reports shall include documentation of all challenges to safety and relief valves.
6.9.1.5.3 Reports shall include the results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.5.
The fol-lowing information shall be included:
(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radiofodine performed prior to exceeding the limit, results of analysis while the limit was exceeded, and results of one analysis after the radiciodine activity was reduced to less than the limit E single submittal may be made for a multiple unit station.
The submittal A
should combine those sections that are common to all units at the ' station.
UThis tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
GRAND GULF-UNIT 1 6-16 AmendmentNo.28l