ML20216J328
| ML20216J328 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 04/16/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216J321 | List: |
| References | |
| R-028-A-044, R-28-A-44, NUDOCS 9804210355 | |
| Download: ML20216J328 (7) | |
Text
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puco 33 lt UNITED STATES 3
- .}2 NUCLEAR REGULATOHY COMMISSION WASHINGTON, D.C. 2066H001 4
9 . . . . . ,o UNIVERSITY OF MICHIGAN DOCKET NO. 50-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. R-28
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application filed by the University of Michigan (the licensee), dated April 2, 1998, 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 1:
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 and publication of notice for this amendment is not required by 10 CFR 2.106.
- 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-28 is hereby amended to read as follows:
9804210355 980416 PDR ADOCK 05000002 P PDR 2
A 2
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, 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 i h Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: April 16, 1998 i
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l ENCLOSURE TO LICENSE AMENDMENT NO. 44 l
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. FACILITY OPERATING LICENSE NO. R-28 l
DOCKET NO. 50-2 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and are underlined to indicate the area of change.
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OPERAT:NG LICENSE AND TECHNICAL SPECIFICATIONS
- *- Forc 'uclear Reactor Docket 50-2. License R-28 Amencment 44: Proposea 2.1.2 Safety Limits in the Natural Convection Mode Applicability:
This specification applies to the interrelatea variables associated with core thermal and hydraulic performance in the natural convection mode of operation. These variables are:
Reactor Thermal Power, P Reactor Coolant Inlet Temperature. Ti Height of Water Above the Top of the Core, H Objective:
To assure that the integrity of the fuel elad is maintained.
Specification:
- 1. The true value of the reactor thermal power (P) shall not exceed 380 kw.
2.
The true value of the reactor coolant inlet temperature (TA ) shall not exceed 131 F.
- 3. The height of pool water above the core (H) l shall not be less than 18 feet.
Bases:
The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact FNR core (25 elements) will not reach the boiling point of the water coolant at a depth of 18 feet.
2.2 Limiting Safety System Settings (LSSS) 2.2.1 Limiting Safety System Setting in the Forced Convection Mode Applicability:
This specification applies to the set points for the safety channels monitoring reactor thermal power (P), primary coolant flow (m),
height of water above the top of the core (H), l44 core exit temperature (T I and core inlet temperature (Ti).
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i vethA11NG LICENSE AND TECHNICAL SPECIFICATIONS Foro Nuclear Reactor '
,- - Docket 50-2, License R-28 Amencment 44: Proposed Objective:
To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
Specification:
- 1. The limiting safety system settings for I reactor thermal power (P), primary coolant flow through the core (m), height of water above the top of the core (H), and reactor coolant exit temperature (T.) shall be as I follows: 4 l
Variable LSSS P (Max) 2.60 Mw l39 m (Min) 900 gpm H (Min) 19 ft T.(Max) 129 oF
- 2. The limiting safety system setting for l44 reactor coolant inlet temperature at tpermal power levels above 1.6 Mw shall be:
Ti (max) = 114 oF
[44 Bases:
The limiting safety system settings for forced convection assure that automatic protective action will correct the most severe abnormal situation anticipated before a safety limit is exceeded.
2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability:
These specifications apply to the setpoint for the safety channels monitoring reactor thermal i power (P), pool water level (H), and pool water temperature (T).
Objective:
l i To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Foro Nuclear Reactor Decket 50-2 License R-28 Amendment 44: Proposed Table 3.1 REQUIRED SAFETY CHANNELS Minimum Number Channel Setooint Reauired Function tog Count Rate 2 cps 1 Rod Withdrawal Interlock Log N Period- 1 Wide range power level, power level l44 interlocks, and input [
for period scram Period Safety 5 see 1 Scram Level Safety 122.5% (2.45 Mw) 2 Scram l39 High Power /No (a) 900 gpm 1 Water Flow (b) holdup tank Scram 1100 kw isolation valve not fully open (c) holdup tank static pressure 1 psig below full power value High Power /
Header Down 1 l
Scram 1100 kw l Header Up/ 900 gpm 1 Scram l No Water Flow Building Exhaust 1 mrem /hr 1 Scram i
Radiation Level Buildihg Alarm 1 Scram Manual Switch Manual Sc'am r Switch 1 Scram Magnet Power Keyswitch 1 Scram Reactor Coolant Inlet Temp. 114 oF l44 ,
1 Auto Rundown 2 1.6 MW l Reactor Coolant Exit Temp. 129 oF 1 Auto Rundown Reactor pool Temperature 44 129 oF 1 Auto Rundown Page 13
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- OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuc10er Reactor
- Docket 50-2 License R-28 Amendment 44: Proposed Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram will occur in theatevent is operating poweroflevels a lossabove of flow 100when kw. the reactor The rod withdrawal interlock on the Log Count Rate channel assures that the operator has a measuring channel operating and indicating neutron fl ux levels during the approach to criticality.
The reactor coolant inlet temperature, reactor coolant l44 exit temperature, reactor pool temperature auto rundown functions and the pool level auto rundown assure that the reactor will not be operated above the l eafety limit for core inlet temperature and below the i safety limit for pool level in either natural or 44
] forced convection mode.
The manual scram button and the magnet power keyswitch provide two methods for the reactor operator to j manua31y shutdown the reactor if an unsafe or abnormal l
condition should occur and the automatic reactor protection does not function.
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l The use of the area radiation monitor system assures that areas of the facility in which a high radiation area could exist are monitored.
Specifications 3.2.2 and 3.2.3 assure that the l
safety system response will be appropriate. l l
Mechanical holddown devices specified in 3.2.4 ensure 38 )
that a fuel element cannot be lifted from the core by '
withdrawal of a control rod and be released back into the core resulting in a sudden positive reactivity l insertion.
3.3 FNR Confinement Building l Applicability:
This specification applies to the Ford Nuclear Reactor confinement building requirements.
Objective:
To assure that the Ford Nuclear Reactor Building 38 confinement integrity is maintaine'd during reactor operation and to minimize the release of airborne radioactive materials from the reactor building.
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