ML20204G699
| ML20204G699 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/20/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20204G704 | List: |
| References | |
| DPR-59-A-106 NUDOCS 8703260442 | |
| Download: ML20204G699 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION
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FOWEP - AUTHORITY OF THE STATE OF l'EW YORK DOCKET f:0. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.106 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated December 31, 1986, 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 confornity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasone' ie assurance (i) that the activities authorized C.
s
.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; 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 Operatino License No. DPR-59 is hereby amended to reod as follows:
D703260442 870320 PDR ADOCK 05000333 P
p (2) Technical Specifications The Technical Specifications cor.tained 1.i Arpendices A and'B, as'
. revised through Amendment No.106, are hereby incorporated in the license.
The licensee shall operate the facility in accordarce with the Technical Specifications.
3.
The license amendment is effective-as of the date of its issuance.
FOR THE NUCLEAR REGULAiORY C0f' tICSION
\\
Y hjd Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing 1
Attachment:
Changes to the Technical l
Specifications j
Date of Issuance:
March 20, 1987 t
1
ATTACHMENT TO LICEl:SE AMEND!1Et;T NO.106 FI,CILITY OPEP.ATING LICEl:SE l'0 DPR-59 LLCKET I40. 50-333 Replace the followir.g pages of the Appendix A Technical Specifications with the encloseo pages. The revised areas are indicated by narginal lines.
Pages 54 60 70c 71 79
1 JAFNPP 4.2 (cont'd) 3.2 (cont'd)
E.
Drywell Leak Detection E.
Drywell Leak Detection The limiting conditions of operation for the Instrumentation shall be calibrated and checked inst rumentation that monitors drywell leak as indicated in Table 4.2-5 detection are given in Table 3.2-5.
F.
Surveillance Information Readouts F.
Surveillance Information Readouts The limiting conditions for the instrumentation Instrumentation shall be calibrated and checked that provide (s) surveillance information readouts as indicated in Table 4.2-6 are given in Table 3.2-6.
G.
Recirculation Pump Trip G.
Recirculation Pump Trip The limiting conditions for operation for the Instrumentation shall be functionally tested and inst rumentation that trip (s) the recirculation calibrated as indicated in Table 4.2-7.
pumps as a means of limiting the consequences of a failure to scram during an anticipated tran-System logic shall be functionally tested as in-dicated in Table 4.2-7.
sient are given in Table 3.2-7.
H.
4 kv Emergency Bus Undervoltage Trip The limiting conditions for operation for the instrumentation that prevents damage to electrical equipment or circuits as a result of either a degraded or loss-of-voltage condition on the emergency electrical buses are given in Table 3.2-2.
Amendment No.106 54
,.E
. [..
JAFNPP 3.2 BASES (cont'd)
The recirculation pump trip has been added at the suggestion of ACRS as a means of limiting the conse-quences of the unlikely occurrence of a failure to ceram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events given in General Electric Company Topical Report, NEDO-10349, dated March, 1971.
The Emergency Bus Undervoltage Trip System transfers the 4 kV emergency electrical buses to the Emergency Diesel Generators in the event an undervoltage condition is detected. The system has two levels of protection: (1) degraded voltage protection, and (2) loss-of-voltage protection. Degraded voltage protection prevents a sustained low voltage condition from damaging safety-related equipment. The loss-of-voltage protection prevents a more severe voltage drop from causing a long term interruption of power. Time delays are included in the system to prevent inadvertent transfers due to spurious voltage dscreases. Therefore, both the duration and severity of the voltage drop are sensed by the Emergency Bus Undervoltage Trip System.
l l
Amendment No.106 60
JAFNPP TABLE 3.2-2 (cont'd)
INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Total Minimum No.
Number of Instru-of Operable ment Channels Pro-Instrument vided by Design for Item Channels Per No.
Trip System (1)
Trip Function Trip Level Setting Both Trip Systems Remarks 2 Inst. Channels 1.
Initiates 4kV Emerqancy J
37 (1 per 4kV bus) 4kV Emergency Bus 108 1 1.5 Bus Undervoltage DeJraded Undervoltage Relay secondary volts Voltage Timer.
(Degraded Voltage)
- 2. Notes 4 and 6.
2 Inst. Channels
- 1. Note 5.
l 38 (l per 4kV bus) 4kV Emergency Bus 9.0 1 1.0 sec.
I Undervoltage Timer (Degraded Voltage) 2 Inst. Channels 1.
Initiates 4kV Emorgency 39 (1 per 4kV bus) 4kV Emergency Bus 85 1 4.25 Bus Undervoltago Inas Undervoltage Relay secondary volts of Voltage Timer.
(Loss of Voltage)
- 2. Notes 4 and 7.
2 Inst. Channels
- 1. Note 5.
40 (1 per 4kV bus) 4kV Emergency Bus 2.50 1 0.05 sec.
Undervoltage Timer (Loss of Voltage) 4 Inst. Channels Permissive for closing re-Reactor Low Pressure 285 to 335 psig circulation pump dischirge 41 2
valve.
Amendment No. M,f(106, 7g
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JAFNPP TABLE 3.2-2 (Cont'd)
INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS NOTES FOR TABLE 3.2-2 1.
Whenever any ECCS subsystem is required by specification 3.5 to be operable, there shall be two operable trip systems.
From and after the time it is found that the first column cannot be met for one of the trip systems, that trip system shall be placed in the tripped condition or the reactor shall be placed in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
' Deleted" 3.
Refer to Technical Specification 3.5.A for limiting conditions for operation, failure of one (1) instcument channel disables one (1) pump.
4.
Tripping of 2 out of 2 sensors is required for an undervoltage trip. With one operable sensor, operation may continue with the inoperable sensor in the tripped condition.
5.
The 4kV Emergency Bus Undervoltage Timers (degraded voltage and loss-of-voltage) initiate the following: initiates the start of the Emergency Diesel-Generators; trips the normal / reserve tie breakers and trips all 4kV motor breakers (in conjunction with 75 percent Emergency Diesel-Generator voltages); initiates diesel-generator breaker closes permissive (in conjunction with 90 percent Emergency Diesel-Generator voltages) and; initiates sequential starting of vital loads in conjunction with low-low-low reactor water level or high drywell pressure.
6.
A secondary voltage of 108 volts corresponds to approximately 90.8% of 4160 volts on the bus.
7.
A secondary voltage of 85 volts corresponds to approximately 71.5% of 4160 volts on the bus.
l l
g,105 Amendment No.
71
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+ ' * ~
TABLE 4.2-2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CORE AND CONTAINMENT COOLING SYSTEMS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check (4) 1)
Reactor Water Level (1)(5)
(15)
Once/ day 2a)
Drywell Pressure (non-ATTS)
(1)
Once/3 months None 2b)
Drywell Pressure (ATTS)
(1)(5)
(15)
Once/ day 3a) Reactor Pressure (non-ATTS)
(1)
Once/3 months None 3b)
Reactor Pressure (ATTS)
(1)(5)
(15)
Once/ day.
4)
Auto Sequencing Timers None Once/ operating cycle None 5)
(1)
Once/3 months None 6)
Trip System Bus Power Monitors (1)
None None 8)
Core Spray Sparger d/p (1)
Once/3 months Once/ day 9)
Steam Line High Flow (HPCI & RCIC)
(1)(5)
(15)
Once/ day 10)
Steam Line/ Area High Temp. (HPCI & RCIC)
(1)(5)
(15)
Once/ day 12)
HPCI & RCIC Steam Line Low Pressure (1)(5)
(15)
Once/ day 1
13)
HPCI & RCIC Suction Source Levels (1)
Once/3 months None I
14a) 4KV Emergency Bus Under-Voltage Once/ operating cycle Once/ operating cycle None
( Loss-of-Voltage ) Relays and Timers 14b) 4KV Emergency Bus Under-Voltage Once/ operating cycle Once/ operating cycle None (Degraded voltage) Relays and Timers 15)
HPCI & RCIC Exhaust Diaphragm (1)
Once/3 months None Pressure High 17)
LPCI/ Cross Connect Valve Position Once/ operating cycle None Mon.*
NOTE:
See listing of notes following Table 4.2-6 for the notes referred to herein.
Amendment No. J/, M, M, 79' 106 79
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