ML20080G516
| ML20080G516 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/30/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080G518 | List: |
| References | |
| NUDOCS 9502080126 | |
| Download: ML20080G516 (6) | |
Text
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION
'2 WASHINGTON, D.C. 30686-0001
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 223 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated September 28, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 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 Commiission's regulations; 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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. DPR-59 is hereby amended to read as follows:
9502080126 950130 PDR ADOCK 05000333 P
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 223, 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 its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COP 911SSION Ledyard B. Narsh, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 30, 1995
F ATTACHMENT TO LICENSE AMENDMENT NO. 223 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Paces Insert Paaes 240 240 243 243 244 244 l
JAFNPP 3.11 (cont'd) 4.11 (cont'd)
D.
Emeroency Service Water System D.
Emeroency Service Water System 1.
To ensure adequate equipment and area cooling, both 1.
Surveillance of the ESW system shall be performed as ESW systems shall be operable when the requirements of follows:
specification 3.5.A and 3.5.B must be satisfied, except as specified below in specification 3.11.D.2.
Item Frecuency a.
Simulated Automatic Each operating cycle Actuation Test b.
Flow Rate Test - Each ESW Once/3 months pump shall deliver at least 1500 gpm to its respective loop. The pump total developed head shall be greater than or e to the corresponding poin' pump curve, reduced by a maximum of 7%, for the measured flow.
c.
Pump Operability Once/ month d.
Motor Operated Valves Once/ month i
l Amendment No. [,1/4, 223 l
240 l
l
JAFNPP-3.11 & 4.11 BASES A.
Main Control Room Ventilation System B.
Crescent Area Ventilation 4
1 One main control room emergency ventilation air supply fan Engineering analyses indicate that the temperature rise in provides adequate ventilation flow under accident conditions.
safeguards compartments without adequate ventilation flow or -
Should one emergency ventilation air supply fan and/or fresh cooling is such that continued operation of the safeguards air filter train be out of service during reactor operation, a equipment or associated auxiliary equipment cannot be 4
repair time of 14 days is allowed because during that time, a assured.
redundant 100% capacity train is required to be operable.
C.
Batterv Room Ventilation The 3 month test interval for the main control room emergency ventilation air supply fan and dumpers is sufficient Engineering analyses indicate that the temperature rise and i
since two redundant trains are provided and neither is normally hydrogen buildup in the battery, and battery chargar in operation.
compartments without adequate ventilation is such that continuous operation of equipment in these compartments A pressure drop test across each filter and across the filter cannot be assured.
system is a measure of filter system condition. DOP injection i
measures particulate removal efficiency of the high efficiency D.
Emeroency Service Water System particulate filters. A Freon-112 test of charcoal filters is essentially a leakage test. Since the filters have charcoal of The ESWS has two 100 percent cooling capacity pumps, each known efficier.cy and holding capacity for elementaliodine powered from a separate standby power supply. The ESW and/or methyl iodine, the test also gives an indication of the system supplies lake water to cool equipment required to relative efficiency of the installed system. Laboratory analysis function following an accident. This equipment consists of:
of a sample of the charcoal filters positively demonstrates emergency diesel generators, electric bay unit coolers, cable halogen removal efficiency. These tests are conducted in tunnet/ emergency switchgear room coolers, crescent area accordance with manufacturers' recommendations.
coolers, control room air handling units and relay room air handling units. Emergency service water is initially supplied to j
The purpose of the emergency ventilation air supply system the control room chillers and chiller room air handling units l
capacity test is to assure that sufficient air is supplied to the unless ESW is manually realigned to supply the control room
" i, main control room so that a slight positive pressure can be and relay room air handling units. ESW will also supply water maintained, thereby minimizing in-leakage.
to the control rod drive pump coolers which are not t
automatically isolated following an accident. The surveillance requirement compares pump performance with the pump curve to determine pump operability. It also specifies testing at a l
L 1[,223 Amendment No.1 243 w.~
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JAFNPP 3.11 and 4.11 BASES (cont'd) flow rate greater than the minimum flow necessary to cool the equipment listed above. The minimum flow requirement was determined from calculations and testing to validate flow and/or heat removal capability at a maximum design lake water ;emperature.
E.
Intake Deicina Heaters The general objective of this specification is to ensure adequate water (30,000 gpm Ref FSAR Q.2.1 is available to the ESW and RHRSW systems to fulfill the cooling requirements of the associated ECCS loads. Since it is required that an opening large enough to satisfv the demand (10% of the total area) be preserved, it is justifiable to assume that no more than 20% of the heaters be available at anytime.
The weekly check of G heater feeder ammeters shall Se made to prove that the system is supplying adequate heGc to the bar racks. If a major deviation from rated current is detected, heater breakers can be cf.ecked to see if they have tripped or the individual heaters can be tested for open circuits.
The semiannual check of each heater will verify that the weekly tests have been adequate. The annual check of circuit meggar readings will check against long term degradation of circuit insulations.
Amendment No. 223 244