ML20246E124
| ML20246E124 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/03/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246E127 | List: |
| References | |
| NUDOCS 8907120117 | |
| Download: ML20246E124 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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SYSTEMS ENERGY RESOURCES INC., et al.
DOCKET N0. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.60 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by System Energy Resources, Inc.,
(the licensee), dated April 18, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the ccmon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 60, are hereby incorporated into this
. license. System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 3,1989 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. NPF-i?
DU XET NO. 50-416 Replace the follcwing pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
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1 INSTRUMENTATION BASES 3/4.3.7.10- LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The system consists of 16 sensors, of which only~8 are selected and need to be OPERABLE at a time, to provide the inputs to the 8 monitoring channels.
The remaining 8 sensors may be used as replacement sensor inputs for failed sensors or to provide a change in location of the area being monitored.
The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.11 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance l
with the procedures in the ODCM to ensure that the alarm / trip will occur prior
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to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.
~
3/4.3.7.12 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and. control, as applicable, gaseous effluents during actual or poten-tial releases.
Those. instruments that monitor the activity of gaseous efflu-ents being released to the environment shall have their alarm / trip setpoints calculated in accordance with the methods in the ODCM to ensure that the alarm /
trip will' occur prior to exceeding the limits of 10 CFR Part 20.
Other instru-ments that monitor offgas processing, (i.e., the Explosive Gas Monitor, Offgas 1
Pre-Treatment Monitor, and Offgas Post-Treatment Monitor) are calibrated accord-ing to plant procedures.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.8 PLANT SYSTEMS ACTUATION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action to mitigate the consequences of accidents that are beyond the ability of the operator to control.
The LPCI mode of the RHR system is automatically initiated on a high drywell pressure signal and/or a low reactor water level, level 1, signal. The containment spray system will then actuate automatically following high drywell and high containment pressure signals.
Negative barometric pres-sure fluctuations are accounted for in the trip setpoints and allowable values specified for drywell and containment pressure-high.
A 10-minute minimum, 13-minute maximum time delay exists between initiation of LPCI and containment spray actuation. A high reactor water level, level 8, signal will actuate the feedwater system / main turbine trip system.
The suppression pool makeup system is automatically initiated on a low low suppression pool water level signal with a concurrent LOCA signal or following a specified time delay after receipt of a LOCA signal.
The low low suppression pool water level Trip Setpoint and Allowable Value are relative to the surface floor of the suppression pool (93'Oh" above mean sea level).
GRAND GULF-UNIl 1 B 3/4 3-6 Amendment No.60
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