ML20056F771
| ML20056F771 | |
| Person / Time | |
|---|---|
| Site: | Ohio State University |
| Issue date: | 08/23/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056F770 | List: |
| References | |
| R-075-A-014, R-75-A-14, NUDOCS 9308310037 | |
| Download: ML20056F771 (4) | |
Text
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[e o UNITED STATES
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~ ,j NUCLEAR REGULATORY COMMISSION gA 1 E WASHINGTON D. C. 205ES o,,%'v f g .....f I
OHIO STATE UNIVERSITY i
DOCKET NO. 50-150 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 License No. R-75
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: !
A. The application for amendment to Facility Operating License No. R-75, filed by the Ohio State University (the licensee), dated May 5, 1993, complies with the standards and requirements of the Atomic Energy Act '
of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 regulations of the Commission; 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 regulations of the Commission and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105(a)(4) and publication of notice for this amendment is not required by 10 CFR 2.106(a)(2).
9308310037 930823 PDR ADDCK 05000150 P PDR
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 3.B of facility Operating License No. R-75 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 14, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
, W "
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes i
Date of Issuance: August 23, 1993 i I
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ENCLOSURE TO LICENSE AMENDMENT NO. 14 !
1 FACILITY OPERATING LICENSE NO. R-75 1
DOCKET NO. 50-150 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contain i vertical lines indicating the areas of change. j i
j l Remove- Insert l
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Reactor Safety System Minimum Function Component / Channel i Recuired -
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- 11. Safety Set Points On 4 Slow scram if associated Recorders recorder values are exceeded
- a. Period j[ 5 sec
-i
- b. Linear Level > 120% of licensed power
- c. Linear Level Servo deviation 2, Set point ,
(nominal 20%) !
- d. Start-Up Channel ji 2 cts /sec (may be bypassed if R,gg < 0.9) '
- 12. Safety System 2 Slow scram in case of a safety amp fault or if L system is discontinuous
- 13. Backup Shutdown 3 Rod drop will occur for Mechanisms any control rod which has excess magnet current 2.100 na ;
i Bases: ,
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- 1. Assures safety ]Imit is not exceeded; core inlet temperature is same as cooling system outlet j
- 2. Assures safety limit is not exceeded
- 3. Assures safety ]Jait is not exceeded l
- 4. Assures coolant system pumps are functjonal before raising power > f 120 kw.
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- 5. Assures there is always primary coolant flow when greater than 120 {
kw. !
- 6. Assures there is enough primary coolant for natural convection cooling
- 7. Assures nuclear instrumentation is in proper mode for operatjon !
- 8. Assures informa13on is available for observation by the reactor l operator during operation, and is recorded if required as a record of I reactor operations i
- 9. Assures that the reactor can be shut down by the reactor operator in i the control room or at other locations near experimental facilitjes if '
deemed necessary by other reactor staff
- 10. ;
Assures shutdown if nuclear instrumentation fails
- 11. Assures backup shutdown capability from short period or high power level. Assures shutdown if servo operation varies too greatly.
Assures shutdown if count rate is too low to provide meaningful startup i information. The startup Interlock may be bypassed if K is < .9
- 12. Assures all components of the safety system are 'fnstalled and !
operational
- 13. Assures that any control rod exhibiting excess magnet current will be released and fall to the bottom due to gravity 5 i
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/JiENDMENT NO.14