ML20214Q962
| ML20214Q962 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 11/24/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214Q935 | List: |
| References | |
| R-70-A-009, R-70-A-9, NUDOCS 8612050327 | |
| Download: ML20214Q962 (8) | |
Text
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- 'o g UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION
$ $ WASHINGTON, D. C. 20555
\...../ _
THE UNIVERSITY OF MARYLAND DOCKET NO. 50-166 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. R-70
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment to Facility Operating License No. R-70, filed by the University of Maryland (the licensee), dated August 26, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the amended license, the provisions of the Act, and the rules and regulations of the Comission; ,
C. There is reasonr.ble assurance: (1) 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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulatic,ns and all applicable requirements have
- been satisfied; and
[
l F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
8612050327 861124 PDR ADOCK 05000166 P PDR
- 2. 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 License No. R-70 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance.
F0 THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Appendix A Technical Specifications Changes Date of Issuance: NOV 2 41985 i ,
i l
ATTACHMENT TO LICENSE AMENDMENT NO. 9 FACILITY OPERATING LICENSE NO. R-70 DOCKET NO. 50-166 Revised Appendix A Technical Specifications are as follows:
- Remove Pages Add Pages
- 21 21 (Amendment No. 9) 22 22 (Amendment No. 9) 25 25 (Amendment No. 9 26 26 (Amendment No. 9 27 27 (Amendment No. 9 Changes on the revised pages are identified by marginal lines.
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ADMINISTRATIVE ORGANIZATION President '
University of Maryland -
p-Chancellor College Park Campus .,
e
+ s-Dean Vice Chancellor College of for Engineering Admin. Affairs ir Chairman Chemical & -
Nuclear Engineering Department 3r 3r y .
4 l Director Reactor member Director Radiation Nuclear. <g. Sa fe ty <--.. Environmental ... Safety
! Reactor , Committee Safety Dept./ Committee (audits & Radiation Safety '
reviews) '
Officer ,
I i
e.
l Reactor i Asst. Radiation Operations ' - - services Safety Staff Officer i I
l v
Radlatton
( Safety Office Staff l
Fig. 6-1 I
21 Amendment tio. 9 ,
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l I
HUTR ORGANIZATIONAL STRUCTURE
. Dean College of Engineering ..
+
Chairman -
Department of Chemical and Nuclear Engineering E V I
Director Reactor Nuclear Reactor 4--* Safe ty Committee (Facility Director) .
Senior Reactor Operator Reactor Operator J
i Fig. 6-2 l
l 22 i Amendment No_9
- c. Maintenance procedures 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.
Substantive changes to the above procedures may be made with the approval of the Facility Director. All such temporary changes to procedures shall be documented and subsequently reviewed by the Reactor Safety Committee.
6.4 EXPERIMENT REVIEW AND APPROVAL (1) Routine experiments may be performed at the discretion of the duty
. senior reactor operator without the necessity of any further review or approval. ,,
(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 RSC 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 possibility and u consequences of its failure, including, where significant, consideration-of chemical reactions, physical integrity, design life, proper cooling, interaction with core components, and reactivity effects.
6.5 REQUIRED ACTIONS .
6.5.1 ACTIONS TO BE TAKEN IN TE!E EVENT OF A ItEPORT.\BLE OCCURRENCE In the event of a reportable occurrence, as defined in these Technical Specifications, the following actions will be taken:
(t) Immediate action will be taken to correct the situation and to mitigate the consequences of the occurrence. e.
(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 to the NRC and Dean, College of Engineering. The report shall include l an analysis of the causes of the occurrence, the effectiveness of corrective actions taken, and recommendations of measures to prevent or reduce the probability or consequences of recurrence.
6.5.2 ACTION TO DE TAKEN IN Tile EVENT A SAFETY I,lMIT IS EXCEEDED in the event a safety limit is exceeded:
25 i AmendmefLt Nom 9
(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 6.6.2 of these specifications, ant!
(c) 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 repo.t shall be submitted to the Reactor Safety Comittee for review and then submitted to the NRC when authorization is sought to resume operation of the reactor.
6.6 REPORTS 6.6.1 ANNUAL OPERATING REPORT A report summarizing facility operations will be prepared annually for the reporting period ending June 30th. This report shall be submitted l by September 30 of each year to the Director, Office of Nuclear Reactor Regulation, NRC, with a copy to the Regional Administrator, Region I, NRC. The report shall include the following:
(1) A brief narrative summary of results of surveillance tests and inspections required in section 4.0 of these Technical Specifications.
(2) A tabulation showing the energy generated in megawatt-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 a description of the facility in the Final Safety Analysis Report and (b) review of changes, tests, and experiments made pursuant to 10 CFR 50.59.
(6) A summary of the nature and amount of radioactive effluents released or discharged to the environment.
(7) A description of any environmental surveys performed outside of the facili ty.
(8) A summary of exposure received by facility personnel and visitors where such exposures are greater than 25 percent of limits allowed by 10 CFR 20.
(9) Changes in facility organization.
Amendment No. 9
3 6.6.2 REPORTABLE OCCURRENCE REPORTS 4
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 the Regional Administrator, Region I, NRC, followed by a written i report within 14 days in the event of a reportable occurrence, as defined in Section 1.0. The written report shall be sent to the Director, Office of Nuclear Reactor Regulation, NRC, with a copy to the Regional Administrator, Region I, NRC. The written report and, to the extent possible, the preliminary telephone or telegraph notification 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 to prevent repetition of the occurrence including changes to procedures (4) evaluate the safety implications of the incident in light of the cumulative experience obtained from the report of previous failure and malfunction of similar systems and components.
6.6.3 UNUSUAL EVENT REPORT A written report shall be forwarded within 30 days to the Director, Office of Nuclear Reactor Regulation, NRC, with a copy to the Regional Administrator, Region I, NRC, in the event of:
(1) discovery of any substantial errors in the transient or accident analysis or in the methods used for such analysis as described in the Safety Analysis Report or in the bases for the Technical I 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 capability of the system to perform its safety function.
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6.7 RECORDS (1) Retraining and requalification records of current 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 years:
(a) normal reactor facility operation and maintenance (b) reportable occurrences (c) surveillance activities required by Technical Specifications (d) facility radiation and contamination surveys (e) incore experiments l
Amendment No. 9
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