ML20080L647
| ML20080L647 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 09/28/1983 |
| From: | IOWA STATE UNIV., AMES, IA |
| To: | |
| Shared Package | |
| ML20080L643 | List: |
| References | |
| NUDOCS 8310030100 | |
| Download: ML20080L647 (4) | |
Text
'
6.0 ADMINISTRATIVE CONTROLS (Continued) 6.5 Required Actions 6.5.1 Action to be Taken in Case of Safety Limit Violation (1) The reactor shall be shut down and I eactor operations shall not be resumed until authorized by the Nuclear Regulatory Commission (NRC).
(2) The safety limit violation shall be promptly reported to the Reactor Manager or a designated alternate.
(3) The safety limit violation shall be reported to NRC.
(4) A safety limit violation report shall be prepared. The repoat, and any follow-up report, shall be reviewed by the Reactor Use Committee and shall be submitted to the NRC when authorization is sought to resume operation of the reactor. The report shall describe the following:
- a. Applicable circumstances leading to the violation including, when known, the cause and contributing f actors,
- b. Ef f ect of the violation upon reactor f acili ty components, systems, or structures and on the health and safety of personnel and the public.
- c. Corrective action to be taken to prevent recurrence.
6.5.2 Action to be Taken in the Event of an Occurrence of the Type Identified in 6.6.2(1)b. and 6.6.2(1)c.
(1) Reactor conditions shall be returned to normal or the reactor shall be shut down. If it is necessary to shut doun the reactor to correct the occurrence, operations shall not be resumed unless authorized by the Reactor Manager or a designated alternate.
(2) Occurrence shall be reported to the Reactor Mananar an a designated alternate and to the NRC.
(3) Occurrence shall be reviewed by the Rearior Use Committee at its next scheduled meeting.
d-7 8310030100 830928 PDR ADOCK 05000116 P PDR
+ -
,, o 6.0 ADMINISTRATIVE CONTROLS-(Continued)
'd.6 Reports i
i 6.6.1 Operating Reports
- 'A routine operating report providing the follmaing information shall be submitted to the Nuclear Regulatory Commission in accordance with the provisions of 10 CFR 50.59 at the end of each 12-month period
(1) A narrative summary of. reactor operating experience including the energy produced by the reactor.
4 (2) The unscheduled shutdowns including, where applicable, corrective i action taken to preclude recurrence.
(3) Tabulation of major preventive and corrective maintenance operations having safety significance.
(4) Tabulation of major changes in the reactor facility and procedures, and tablulation of new tests or experiments, or both,
- that are significantly dif ferent from those perf ormed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were involved.
(5) A summary of the nature and amount of radioactive ef fluents released or dischardec: to the environs beyond the effective i control of the owner-operator as determined at or before the
! point'of such release or discharge. The summary shall include to l ~the extent practicable an estimate of individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25 percent of the concentration allowed or recommended, a statement to this effect is sufficient.
i (6) A summarized result of any environmental surveys performed outside the facility.
(7) A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed or recorrenended.
6.6.2 Special Reports i
I. (1) There shall be a report not later than the following working day l by telephone to the appropriate NRC Regional Office and confirmed l in writing by telegraph or simpiar conveyance to the appropriate NRC Regional Office with a copy to the Director of :nspection and Enforcement to be followed by a written report that describes the circumstances of the event within 14 days of any of the l follmaing:
l 6-8
- a. Violation of safety limits (see 6.5.1).
~b. Release of radioactivity from the site above allowed limits (see.6.5.2).
- c. Any of the following (see 6.5.2):
(i) Operation with~ actual safety system settings for required systems less conservative than the limiting safety system settings specified in the Technical Specifications.
(ii) Operation in violation of limiting conditions for operation established in the Technical Specifications unless prompt remedial action is.taken.
(iii) A reactor safety system component malfunction which renders or could render.the system incapable of performing its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reacter shutdown.
(iv) An unanticipated or urcontrolled change in reactivity greater than the licensed excess reactivity, ior one dollar, whichever is smaller.
(v) Abnormal and significant degradation in reactor fuel, or cladding, or both, or coolant boundary which could result in exceeding prescribed radiation exposure limits of personnel or environment, or both.
(vi) An observed inadequacy in the implementation of adninistrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations.
(2) A written report within 30 days to the appropriate NRC Regional Office with a copy to the Director of Inspection and Enforcement concerning the following:
- a. Permanent changes in the organization involving the Nuclear Engineering Department Executive Officer, Reactor Manager, or Radiation Safety Officer.
I b. Significant-changes in the transient or accident analysis as l described in the Safety Analysis Report.
l i
d-9 i
,. i 6.0 ADMINSTRATIVE CONTROLS 6.7 Records 6.7.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component if Less than Five Years (1) Normal reactor facility operation (but not including supporting documents such as checklists, 109 sheets, etc., which shall be maintained for a period of at least one year).
(2) Principal maintenance operations.
(3) Reportable occurrences.
(4) Surveillance activities required by the Technical Specifications.
(5) Reactor facility radiation and contamination surveys where required by applicable regulations.
(6) Experiments performed with the reactor.
(7) Fuel inventories, receipts, and shipments.
(8) Approved changes in operating procedures.
(9) Records of meetings and audit reports of the Reactor Use Committee.
6.7.2 Records to be Retained for at least One Training Cycle Retraining and requalification of licensed operators: Records of the most recent complete cycle shall be maintained at all times the individual is employed.
6.7.3 Records to be Retained for the Lifetime of the Reactor Facility Applicable annual reports, it they contain all of the required information, may be used as records in this section.
(1) Gaseous and liquid radioactive effluents released to the environs.
(2) Off-site environmental monitoring surveys required by the Tecnnical Specifications.
(3) Radiation exposure for all personnel monitored.
(4) Drawings of the reactor facility.
6-10