ML20140H733

Amend 23 to Licensee R-95,removes Reactor Coolant Inlet Temp as TS Requirement in SL & Lsss,Section 2.1.1 & 2.2.1, Respectively

ML20140H733
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	06/17/1997
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20140H727	List: ML20140H724 ML20140H733 ML20140H740
References
R-095-A-023, R-95-A-23, NUDOCS 9706180434
Download: ML20140H733 (7)

Text

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t UNITED STATES g

j NUCLEAR REGULATORY COMMISSION p

't WASHINGTON, D.C. 20066 4 001

+9..... 4 0

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RHODE ISLAND ATOMIC ENERGY COMMISSION l

DOCKET NO. 50-193 AMENDMENT TO FACILITY LICENSE j

Amendment No. 23 License No. R-95 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

j A.

The application for amendment filed by the Rhode Island Atomic Energy Commission, (the licensee), dated June 6, 1997, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the l

provisions of the Act, and the rules and regulations of the Commission; C.

There i; 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 rules and regulations of the Commission; D.

The issuance of this amendment will not be inimical to the common l

defense and security or to the health and safety of the public; E.

This amendment is issued in accordance with 10 CFR Part 51 of the i

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.

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I 9706180434 970617 PDR ADOCK 05000193 P

PDR

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i l 2.

Accordingly, the license is amended by changes to the Technical i

l Specifications as indicated in the enclosure to this license amendment, l

and paragraph 3.b. of License No. R-95 is hereby amended to read as follows:

3.b.

Technical Specifications i

The Technical Specification contained in Appendix A, as revised I

through Amendment No. 23 are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective on the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~, c/m s Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning

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Project Directorate j

l Division of Reactor Program Management l

Office of Nuclear Reactor Regulation l

Enclosure:

Appendix A Technical Specifications Change Date of Issuance:

June 17, 1997 l

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.a.

ENCLOSURE TO LICENSE AMENDMENT N0. 21 FACILITY LICENSE NO. R-95 DOCKET NO. 50-193 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contains vertical lines indicating the areas of change.

Remove Paae Insert Paae 12 12 13 13 14 14 22 22 1

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P TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center f

Docket 50-193. License R-95 Revision 1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS I

2.1 Safety Limits l

2.1.1 Safety Limits in the Forced Convection Mode Applicability:

1 This specification applies to the interrelated variables associated with core thermal and hydraulic performance l

in the steady state with forced convection flow.

These i

variables are:

Reactor Thermal Power, P Reactor Coolant Flow through the Core, m Reactor Coolant outlet Temperature, T l

Height of Water Above the Top of the Core, H l

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Objective:

To assure that the integrity of the fuel clad is maintained.

Specifications:

1.

The true value of reactor power (P) shall not exceed 2.4 MW.

2.

The true value of reactor coolant flow (m) shall not be less than 1580 gpm.

3.

The true value of reactor coolant outlet l

temperature (T ) shall not exceed 125"F.

4.

The true value of water height above the top of the core (H) shall not be less than 23.54 feet while the reactor is operating at any power l

level.

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Page 12 Amendment No. 23

.c TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193. License R-95 Revision 1 i

Bases:

The basis for forced convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact core will not be exceeded.

The thermal hydraulic analysis (Part B of the SAR) i shows that if the safety limits are not exceeded the coolant will not reach the onset of nucleate boiling even at the safety limit of 2.4 MW. Additionally, the limit on coolant j

outlet temperature will prevent exceeding the temperature limit for the cleanup system i

resin.

2.1.2 Safety Limits in the Natural Convection Mode Applicability:

l This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the natural convection mode of operation.

These variables are:

Reactor Thermal Power, P Height of Water Above the Top of the Core, H Pool Temperature. Tp Objective:

1.

To assure that the integrity of the fuel clad is maintained.

2.

To assure consistency with other defined safety system parameters.

Specification:

1.

The true value of the reactor thermal power shall not exceed 217 kw.

l 2.

The height of pool water above the core shall not be less than 23.54 feet.

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Page 13 Amendment No. 23

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l TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R.95 Revision !

l 3.

The pool temperature does not exceed 1300F, l

Bases:

l The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact core will not reach nucleate boiling of the water coolant at a pool depth of 23.54 feet.

2.2 Limiting Safety System Settings (LSSS) 2.2.1 Limiting Safety System Setting in the Forced Convection Mode Applicability:

l LEU Fuel Temperature - Forced Convection Mode i

Objective:

This specification applies to the setpoint for the safety channels monitoring reactor power, primary coolant flow, pool level and core inlet and outlet temperatures to j

assure that the maximum fuel temperature permitted is such that no damage to the fuel cladding will result in the forced convection mode.

Specification:

j The limiting safety system settings for reactor l

thermal power (P), primary coolant flow through the core (m), height of water above the top of the core l

(H),

and reactor coolant outlet temperature (T )

o shall be as follows:

2 Parameter LSSS 4

P (Max) 2.30 MW Max m

(Min) 1600.00 gpm i

H (Min) 23.70 ft T

(Max) 121.00F 4

o Page 14 Amendment No. 23

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TECHNICAL SPECIFICATIONS

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Rhode Island Nuclear Science Center Docket 50-193. License R-95 Revision 1 Reactor Reactor Safety Minimum Operating Mode System Component / Channel Required Function in Which Required Bridge Movement 1

Automatic Both Modes l

scram Coolant Gates Open 1

Automatic Forced Convection scram if above 0.1 MW either the coolant riser or l

coolant downcomer i

gates open Detector High Voltage Failure 3

Automatic Both Modes scram if Voltage I

decreases 50V max Log N Period 1

Automatic Both Modes scram if period s4 see No Flow Thermal Column 1

Automatic Forced Convection scram above 0.1 MW Manual Scram 2

Manual Both Modes Switch (console, bridge) scram l

Pool Temperature 1

Automatic Natural Convection i

SC ret: at l

1.2 6'F i

Pace 22 Amendment No. 23