ML20195B341

Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Setting,Limiting Conditions for Operation,Surveillance Requirements,Design Features & Administrative Controls

ML20195B341
Person / Time
Site:	05000112
Issue date:	10/25/1988
From:	OKLAHOMA, UNIV. OF, NORMAN, OK
To:
Shared Package
ML20195B333	List: ML20195B329 ML20195B334 ML20195B341
References
NUDOCS 8811010529
Download: ML20195B341 (7)

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APPENDIX A 4 .

I LICENSE NO. R-53

~ TECHNICAL SPECIFICATIONS EOB, THE UNIVERSITY OF OKLAHOMA' REACTOR MODRI, AGN- 211P (S'.N. 102)

August 31, 1988 e

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PDC P -

v TABLE OF CONTENTS PAGE

. . . . . . . . . . . . . . . . . . . . . 1 1.0 DEFIN.TTIONS.

1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTING . . .

1 3.0 LIMITING CONDITIONS FOR OPERATION. . . . . . . . . . .

1 4.0 . SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . .

5.0 DESIGN FE.ATURES . . . . . . . . . . . . . . . . . . . I 6.0 ADMINISTRATIVE CONTROLS. . . . . . . . . . . . . . . . I 6.1 Organization . . . . . . . . . . . . . . . . . . . I 6.2 Reactor Safety Committ,ee . . . . . . . . . . . . . 1 6.3 Reporting Requirements . . . . . . . . . . . . . . 2 2

6.4 Procedures . . . . . . . . . . . . . . . . . . . .

2 6.5 Records Retention. . . . . . . . . . . . . . . . .

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V 1.0 DEFINITIONS Administrative Gov.troln - the provisions reinted to organization and management personnel requirements, procedures, record keeping reviews and audita, and reporting that a considered necessary to assure safe completions of the dismantling and decommissioning plan.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Not Applienble.. All fuel has been sent to our DOE approved recipient and the console disabled.

3.0 LIMITING CONDITIONS FOR OPERATION Not Applicable. All fuel has been sont to an DOE approved recipient and the console disabled.

4.0 SURVEILLANCE REQUIREMENTS Not Applicable - All fuel has been sent to an DOE approved i recipient. No radionctive material from the dismantled reactor is present in quantitios harmful to the public.

Other radioactive sources are maintained under the terms of the university broad from license.

5.0 DESIGN FEATURES Not Applienble - All fuel has been sent to n DOE approved recipient and the consolo disabled.

6.0 ADMINISTRATIVE CONTROLS 6.1 Org_nnization of Ronnonsibility for the University of Okinhoma Nuclear Reactor - Administrative control of the reactor la diagrammed in Figure 1.

6.1.1 Pronident - Chief Executive Officer of the University 6.1.2 Provont - Chief Academic Officer 6.1.3 Denn of Engineering - Administrative Officer in charge of the College of Engineering

' 6.1.4 University Rndintion_ Safety Officer (RSO) - Hna overall responsibility for radiologioni safety at the Univoraity and ahn11 assure that all technical aspects of the diamantling and decommissioning are completed as requirca.

6.2 Renator Safety Committee - Not Applicable - All nucient fuel han been sent to n DOE approved recipient.

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PRESIDENT OF THE UNIVERSITY OF OKLAHOMA PROVOST DEAN OF THE COLLEGE OF ENGINEERING RADIATION SAFETY OFF" LR FIGURE 1. Administrative Organization for the OU Reactor Decommissioning lA

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6.3 Reporting Requirements 6.3.1 Final Report. A final report describing the results of the DDP will, be submitted upon completion of the DPP requesting an NRC termination survey.

6.3.2 Reportable Occurrences. Reportable occurrences shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mailgram or facsimile transmission to the NRC Operations Center (202) 951-0550, no later than the first work day following the event. A written follow up report describing the reportable occurrence including causes, probable consequences, corrective actions, and measures to prever t recurrence shall be submitted within 14 days. Information provided shall contain narrative material for a complete explanation of the circumstances surrounding the event. The following events shall be reported:

a. Discovery of significant, unexplained increase in radiation or contamination levels within or around the reactor facility or fuel storage area.

b. Abnormal aegradation discovered in protective barriers for the reactor facility or fuel storage area which would compromise the physical security established for protective storage of the reactor and reactor fuel.

6.3.3 Special Reports. Special reports which may be required by the Nuclear Regulatory Commission shall be submitted to the Director of the appropriate NRC Regional Office within the time period specified for each report.

6.4 procedures. There shall be written procedures for the following.

1. personnel radiation protection consistent with 10 CFR 20.

5. Notification of the proper authorities in the event of significant changes in the radiation or contamination

! levels within the facility.

l 6.5 Record Retention

( 6.5.1 SAFSTOR Records. Retention records or logs relative to the following items ahall be kept and retained until the

, license is terminated, unless otherwise specified by the l NRC:

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a. Facility radiation surveys.

b. Inspections of physical barriers.

c. Abnormal occurrences.

d. Environmental Surveys 6.5.2 Prior Facility Operation Records.

Records or logs relative to the following items shall be retained for a period of at least ten years:

a. Operating logs or data which shall identify:

1. Cocpletion of pre-startup checkout, start-up, power changes, and shutdown of the reactor.

2. Installation or removal of fuel elements, control rods, or experiments that could affect core reactivity.

3. Installation or removal of jumpers, special tags or notices, or other temporary changes to reactor safety circuitry.

4. Rod worth measurements and other reactivity measurements,

b. Principal mainten'4nce operations,

c. Reportabic occurrences.

d. Surveillance activities required by technical specifications.

e. Facility radiation and contamination surveys.

f. Rxperiments performed with the reactor.

g. Changes to operating procedures.

6.5.3 Other Records Records or logs relative to the following items shall be retained for the life of the facility, unless otherwise specified by the NRC:

a. Gaseous and liquid radioactive effluents released to the environment.

b. Appropriate off-site environmental monitoring surveys.

c. Fuel inventories and fuel transfers.

d. Radiation exposures for all personnel.

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e. Updated as-built drawings of the facility.

f., Records of transient or operational cycles for those components designed for a limited number of transients or cycles.

g. Records of training and qualifications for members of the facility staff.

h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

1. Records of meetings of the Reactor Safety Committee.

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