ML20147B731
| ML20147B731 | |
| Person / Time | |
|---|---|
| Site: | 05000294 |
| Issue date: | 02/25/1988 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147B704 | List: |
| References | |
| R-114-A-006, R-114-A-6, NUDOCS 8803020173 | |
| Download: ML20147B731 (9) | |
Text
~6 UNITED STATES
! 4't NUCLEAR REGULATORY COMMISSION p; p WASHINGTON, D. C. 20555
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M_ICHIGAN STATE UNIVERSITY DOCKET NO. 50-294 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6-License No. R-114
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment to Facility Operating License No. R-114, filed by Michigan State University (the licensee),
dated December 22, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's regulations 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 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 Commission's regulations set forth in 10 CFR Chapter I; l 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 Comission's regulations and all applicable requirements have l been satisfied; and i
! 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).
8803020173 880225 PDR ADOCK 05000294 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 2.C.2 of Facility Operating License
-No. R-114 is hereby amended to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, 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 dato of issuance.
FOR THE NUCLEAR REGULATORY C0FNISSION E-Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: February 25, 1988 l
i l.
ENCLOSURE TO LICENSE AMENDMENT NO. 6 FACILITY OPERATING LICENSE NO. R-114-DOCKET NO. 50-294 Replace the following peges of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of changes.
Remove Paces Insert Pages 3-1 3-1 3-2 3-2 '
3-3 3-3 4-2 4-2 4-3 4-3 4-4 4-4 l
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3.0 - LIMITING CONDITIONS FOR OPERATION 3.1 NONPULSING OPERATION Applicability
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This specification applies to the energy generated in the reactor during nonpulsing operation.
Objective This objective is to assure that the reactor does not go critical.
Specifications The reactor core is to be maintained with a Keff less than .996 at all times.
Bases This specification is designed to permit control of the reactor in the fulfillment of other Technical Specification requirements e.g.,
section 4.3.2.a without exceeding the limitation of section 3.2.
3.2 REACTIVITY LIMITATIONS Applicability These specifications apply to the reactivity condition of the reactor and the reactivity worths of control rods and experiments.
They apply for all modes of operations.
Objective
. The objective is to assure that the reactor can be shut down at all times and to assure that the fuel temperature safety limit will not be exceeded.
Specifications
- a. The reactor shall not be operated unless the shutdown margin provided by control rods shall be greater than 0.4% AK/K with:
(1) the highest worth non-secured experiment in its most reactive state.
(2) the highest worth control rod fully withdrawn; and (3) the reactor in the cold critical condition without Xenon.
- b. The excess reactivity above cold critical, without Xenon, shall not exceed 2.25% AK/K with expuriments in place.
3-1 Rev. 3, 2/88
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- c. The maximum rate of reactivity insertion associated with movement of a-standard control rod shall be no greater than l
0.2% A K/K/sec.
Bases
- a. The value of the shutdown margin assures that the reactor can be shut down from any operating condition even if the highest worth control rod should remain in the fully withdrawn position.
- b. The value for maximum excess reactivity provides an adequate margin for experiment insertion while minimizing the possibi-lity of exceeding the safety limits.
- c. The linit on maximum rate of reactivity insertion assures that achieving super-criticality is dependent upon prompt and delayed neutrons rather than prompt neutrons alone.
3.3 PULSE MODE OPERATION Applicability This specification applies to the energy generated in the reactor as a result of a pulse insertion of reactivity.
Objective The objective is to assure that the reactor is not pulsed.
Specification The reactor will not be operated in a pulsed mode.
Bases, This section would ordinarily be removed since operation of the reactor in any mode is not being planned. It has been revised
, to maintain this section available and not to change other section numbers in this series.
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3-2 Rev. 2, 2/88
o 3.4 CONTROL AND SAFETY SYSTEM 3.4.1 Scram Time Applicability This specification applies to the time required for the scrammable control rods to be fuliy_ inserted from the instant that a safety channei variable reaches the Safety System Setting. .
Objective The objective is to achieve prompt shutdown of the reactor to prevent fuei damage.
Specifications The scram time measured from_the instant a simulated signal reaches the vaiue of the LSSS to che instant that the contrui rod reaches its fully inserted position shall not exceed 2 seconds for the pu,s;
-(transient) rod and 1 second for the regular and shim rods, 3-3 Rev. 2, 2/88
Specifications
- a. Whenever a reactor scram caused by high fuel element temperature occurs, an evaluation shall be conducted to determine whether the fuel element temperature safety limit was exceeded.
- b. A Channel Check of the fuel element temperature measuring channel shall be made quarterly whenever the reactor is operated by recording a rneasured value of a meaningful temperature indication.
Bases Operational experience with the TRIGA system gives assurance that the thermocouple measurements of fuc1 element tenperatures have been sufficiently reliable to assure accurate indication of this parameter.
4.3 LIMITING CONDITIONS FOR OPERATION 4.3.1 Reactivity Requirements Applicability These specifications apply to the surveillance requirements for reactivity control of experiments and systems.
Objective The objective is to measure and verify the worth, performance, and operability of those systems affecting the reactivity of the reactor.
Specifications
- a. The reactivity worth of an experiment shall be estimated or measured, as appropriate, before reactor operation with said experiment.
- b. The control rods shall be visually inspected for deterioration at intervals not to exceed 2 years.
- c. The transient rod drive cylinder and associated air supply system shall be inspected, cleaned and lubricated as necessary semi-annually at intervals not to exceed 8 months.
- d. (deleted) 4-2 Rev. 2, 2/88 m
Bases The visual inspection of the control rods is made to evaluate corrosion and wear characteristics caused by operation in the reactor. Transient control rod checks and semi-annual maintenance insure proper operation of this control rod.
4.3.2 Control and Safety System Applicability These specifications apply to the surveillance requirements for measurements, tests, and calibrations of the control and safety systems.
Objective The objective is to verify the performance and operability of those systems and components which are directly related to reactor safety.
Specifications
- a. The scram time shall be measured annually but at intervals not to exceed 14 months.
- b. A Channel Test of each of the reactor safety system channels for the intended mode of operation shall be performed prior to each day's operation or prior to each operation extending more than one day.
- c. (deleted)
Bases Measurement of the scram time on an annual basis is a check not only of the scram system electronics, but also is an indication of the capability of the control rods to perform properly. The channel tests will assure that the safety system channels are operable on a daily basis or prior to an extended run.
4-3 Rev. 2, 2/88
4.3.3 Radiation Monitoring System Applicability This specification applies to the surveillance requirements for the area radiation monitoring equipment and the continuous air monitoring system.
' Objective The objective is to assure that the radiation monitoring equipment is operating and to verify the appropriate alarm settings.
Specifications The area radiation monitoring system and the continuous air monitoring system shall be calibrated annually but at intervals not to exceed 14 months and shall be verified to be operable at weekly intervals.
Bases Experience has shown that weekly verification of area radiation and air monitoring system set points in conjunction with annual calibration is adequate to correct for any variation in the system due to a change of operating characteristics over a long time span.
4.3.4 Ventilation System Applicability This specification applies to the building confinement ventilation system.
Objective The objective is to assure the proper operation of the ventilatien system in controlling releases of radioactive material to the uncontrolled environment.
Specifications It shall be verified weekly that the ventilation system is operable in both normal and emergency conditions.
Bases Experience accumulated over several years of operation has demonstrated that the tests of the ventilation system on a weekly basis are sufficient to assure the propor operation of the system and control of the release of redioactive material.
4-4 Rev. 2, 2/88
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