ML20203L803

Proposed Tech Spec Reflecting Recent Changes in Univ Administrative Organizational Structure

ML20203L803
Person / Time
Site:	University of Maryland
Issue date:	08/26/1986
From:	MARYLAND, UNIV. OF, COLLEGE PARK, MD
To:
Shared Package
ML20203L801	List: ML20203L799 ML20203L803
References
NUDOCS 8608290184
Download: ML20203L803 (5)

Text

e, ADMINISTRATIVE ORGANIZATION President University of Maryland 1

l!

Chancellor College Park Campus e

t y Dean Vice Chancellor College of for Engineering Admin. Affairs nf Chairman Chemical &

Nuclear Engineering Department u 3r y Director Reactor member Director Radiation Nuclear < __ Safety <__-. Environmental ,__ Safety Reactor , Committee Safety Dept./ Committee (audits & Radiation Safety

• reviews) i Officer I

'f 3r I

Reactor Asst. Radiation Operations ' - - services- - - - -

Safety Staff Officer v

Radiation Safety Office Staff Revised 8/26/86 Fig. 6-1

. ~

8608290184 860826 PDR ADOCK 05000166 P PDR

,a MUTR ORGANIZATIONAL STRUCTURE Dean College of Engineering Chairman -

Department of Chemical and Nuclear Engineering E V Nuclear Reactor , , _,

Reactor Director Safety Committee v

5 Senior Reactor Operator Reactor Operator Revised 8/26/86 Fig. 6-2 23

r

c. Maintenance p:ocedures which could have an effect on reactor safety.

d. Periodic surveillance of reactor instrumentation and safety systems and area monitors as required by these Technical Specifications.

Substu a changes to the above procedures may be made with the approval of the lity Director. All such temporary changes to procedures shall be doemr .d and subsequently reviewed by the Reactor Safety Committee.

6.4 EXPERIMENT REVIEW AND APPROVAL (1) Itoutine experiments may be performed at the discretion of the duty senior reactor operator witbout the necessity of any further review or npproval.

(2) Modified routine experiments shall be reviewed and approved in writing by the Facility Director, or designated alternate.

(3) Special experiments shall be reviewed by the RSC and approved by the ilSC and the Facility Director or designated alternate prior to initiation.

(4) The review of an experiment listed in subsections (2) and (3) above, shall consider its effect on reactor operation and the passibility and consequences of its failure, inclucing, where significant, consideration of chemical reactions, physical integrity, design life, proper cooling, interaction with ~ core components, and reactivity effects.

6.5 REQUIRED ACTIONS G.5.1 ACTIONS TO BE TAKEN IN TIIR EVENT OF A ilEPollTABI,E OCCURRENCE in the event of a reportable occurrence, as defined in these Technical Specifications, the following actions will be taken:

(1) Immediate action will be taken to corrcet the situation und to mitigate the consequences of the occurrence.

(2) The reactor conditions shall be returned to normal or the reactor shall be shut down.

(3) The Reactor Safety Committee will investigate the causes of the occurrence. The Reactor Safety Committee will report its findings l to the NRC and Dean, College of Engineering. The report shall include I an analysis of the causes of the occurrence, the effectiveness of corrective S/26/86 '

actions taken, and recommendations of measures to prevent or reduce the probability or consequences of recurrence.

G.5.2 ACTION TO DE TAKEN IN TIIE EVENT A SAFETY i,IMIT IS EXCEEDED In the event a safety limit is exceeded:

25

(a) The reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.

(b) An immediate report of the occurrence shall be made to the Chairman, Reactor Safety Committee, and reports shall be made to the NRC in accordance with Section G.6.2 of these specifications, and (e) A report shall be prepared which shall include an analysis of the cause and extent of possible resultant damage, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Reactor Safety Committee for review and then submitted to the NRC when authorization is sought to resume operation of the reactor.

G.G R EPO RTS 6.6.1 ANNU AL OPER ATING REPORT A report summarizing facility operations will be prepared annually for the reporting period ending June 30th. A copy of this report shall be submitted to th l 8/Z6/86 l year,e Regional Administrator, NRC Region I by September 30 of eachwith a copy Reactor Regulation, NRC. The report shall include the following:

(1) A brief narrative summary of results of surveillance tests nnd inspections required in section 4.0 of these Technical Specifications.

(2) .\ tabulation showing the energy generated in megm"att-hours for the year.

(3) A list of unplanned shutdowns including the reasons therefore and corrective action taken, if any.

(4) A tabulation of the major maintenance operations performed during the period, including the effects, if any, on safe operation of the reactor, and the reason for any corrective maintenance required.

(5) A brief description of (a) each change to the facility to the extent that it changes u description of the facility in the Final Safety Analysis Report and (b) review. of changes, tests, and experiments made pursuant to 10 C P R 50.59.

(6) A summary of the nature and amount of radioactive effluents released or discaarged to the environment.

(7) A description of any environmental surveys performed outside of the facility.

(1) A ::ummary of exposure received by facility personnel and visitors where such exposur.'s are greater than 25 percent of limits allowed by 10CF R20.  ;

(9) Changes in facility organi; ation.

26

G.G 2 REPORTABLE OCCURRENCE REPORTS Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to j the Regional Administrator, NRC, Region I followed by a written report /

within 14 days in the event of a reportable occurrence, as defined in Section 8/26/86 1.0. The written report and, to the extent possible, the preliminary telephone or telegraph notifcation shall:

(1) describe analyze, and evaluate safety implications (2) outline the measures taken to ensure that the cause of the condition is determined (3) indicate the corrective action taken tc prevent repetition of the occurrence including changes to procedures (O evaluate the safety implications of the incident in light of the cumulative experience obtained from the report of previr us failure und malfunction of similar systems and components.

G.6.3 UNUSU AL EVENT REPORT l A written report shall be forwarded within 30 days to the Regional J Administrator, NRC, Region Iin the event of: 8/26/86 (1) discoverv of nny substantial errors in the transient or accident analysis or in the methods used for such analysis as de.seribed in the Safety

\nalysis Report or in the basis for the Tcchnical Specifications.

(2) discovery of any substantial variance from performance specifications contained in the Technical Specifications or Safety Analysis Report (3) discovery of any condition involving a possible single failure which, for a system designed against assumed failure, could result in a loss of the enpability of the system to perform its safety function.

G .7 REColt OS (1) Retraining and requalification records of c~urrent licensed operators shall be retained for at least one training cycle.

(2) The following records shall be retained for a period of at least five year",:

(a) normal reactor facility operation and maintenance (b) reportahic occurrences (c) surveillance activities required by Technical Specifications (d) facility radiation and contamination surveys (c) incore experiments 27