ML20086C077
| ML20086C077 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/19/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086C079 | List: |
| References | |
| NUDOCS 9507060267 | |
| Download: ML20086C077 (9) | |
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/1 S1 UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20065-0001 49.....,6 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. 225 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 February 22, 1995, 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 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 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
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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.
i 2.
Accordingly, the license is amended by deleting paragraph 2.E on page 4 of the Facility Operating License No. DPR-59.
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9507060267 950619 PDR ADOCK 05000333 P
... 3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMISSION Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 19, 1995 r-
ATTACIMENT TO LICENSE AMENDMENT NO. 225 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Pages Insert Paaes i
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v 53 53 60a 60a 76 76 84a 84a 9
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JAFNPP TECHNICAL SPECIFICATIONS TABLE OF CONTENTS Einost 1.0 Definitions 1
UMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1-Fuel Cladchng Integrity 2.1 7
1.2 Reactor Coolant System 2.2 27 SURVEILLANCE UMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.0 General 4.0 30 3.1 Reactor Protection System 4.1 30f 3.2 Instrumentation 4.2 49 A.
Primary Containment isolation Functions A.
49 B.
Core and Containment Cooling Systems -
B.
50 initiation and Control C.
Control Rod Block Actuation C.
50 D.
Radiation Monitoring Systems - Isolation D.
50 and Initiation Functions E.
Drywell Leak Detection E.
53 i
F.
Feedwater Pump Turbine and Main Turbine Trip F.
53 l
1 G.
Recirculation Pump Trip G.
53 H.
Accident Monitoring Instrumentation H.
53 i
1.
4kV Emergency Bus Undervoltage Trip 1.
53 J.
Remote Shutdown Capability J.
54 3.3 Reactivity Control 4.3 88 A.
Reactivity Limitations A.
88 B.
Control Rods B.
91 C.
Scram insertion Times C.
95 D.
Reactivity Anomalies D.
96 3.4 Standby Liquid Control System 4.4 105 A.
Normal Operation A.
105 B.
Operation With inoperable Components B.
106 C.
Sodium Pentaborate Solution C.
107 3.5 Core and Containment Cooling Systems 4.5 112 A.
Core Spray and LPCI Systems A.
112 B.
Containment Coolmg Mode of the RHR B.
115
^
System i
C.
HPCI System C.
117 D.
Automatic Depressurization System (ADS)
D.
119 E.
Reactor Core isolation Cooling (RCIC)
E.
121 System Amendment No. 20,100,101,100.100,2:0, 225 i
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y JAFNPP l
LIST OF TABLES IAhlt li1lA EASA 3.1-1 Reactor Protection System (Scram) Instrumentation Requirement 41 3.1-2 Reactor Protection System Irctrumentation Response Times 43a-4.1-1 Reactor Protection System (Scram) Instrument Functional Tests 44 4.1-2 Reactor Protection System (Scram) instrument Calibration 46_
3.2 1 Instrumentation that initiates Primary Containment Isolation 64 i
3.2-2 Instrumentation that initiates or Controls the Core and Containment 66 Cooling Systems i
3.2-3 Instrumentation that Initiates Control Rod Blocks 72 3.2-4 (DELETED) 74 3.2-5 Instrumentation that Monitors Laakage Detection inside the Drywell 75 3.2-6 Foodwater Pump Turbine and Main Turbine Trip Instrumentation Requirements 76 l
3.2-7 Instrumentation that initiates Recirculation Pump Trip 77 3.2-8 Accident Monitoring Instrumentation 77a I
3.2 9 Primary Containment Isolation System Actuation Instrumentation 77e Response Times 3.2 10 Remote Shutdown Capability Instrumentation and Controls 77f 4.21 Minimum Test and Calibration Frequency for PCIS 78 4.2-2 Minimum Test and Calibration Frequency for Core and Containment 79 Cooling System t
4.2-3 Minimum Test and Calibration Frequency for Control Rod Blocks Actuation 81 4.2-4 (DELETED) 82 4.2-5 Minimum Test and Calibration Frequency for Drywell Leak Detection 83 i
4.2 6 Feedwater Pump Turbine and Main Turbine Trip instrumentation Test S4a l
and Calibration Rsquirements 4.2-7 Minimum Test and Calibration Frequency for Recirculation Pump Trip 85 Amendment No. 20, S2, t 20,1S1, t ??,100, 210, 225 v
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JAFNPP 3.2 (cont'd) 4.2 (cont'd)
E.
DrvwaN Laak Detection E.
Drywell Laek Detection The limiting conditions for operation for the instrumentation Instrumentation shall be calibrated and checked as indicated in that monitors drywell leek detection are given in Table 3.2-5.
Table 4.2-5.
F.
Feedwater Pwnn Turtans and Mem Twtune Tno F.
Feedwater Pumn Turbine and Mem furbme Tno The limiting conditions for operation for the instrumentation instrumentaticn shall be tested and calibrated as indicated in that provides a feedwater pump turbine and main turbine trip Table 4.2-6.
are given in Table 3.2-6.
G.
Recuculation Pumn Trio G.
Racerculation Pumn Tno The limiting conditions for operation for the instrumentation Instrumentation shall be functionally tested and calibrated as that trip (s) the recirculation pumps as a means of limiting the indicated in Table 4.2-7.
consequences of a failure to scram dunng an anticipated transsent are given in Table 3.2-7.
System logic shall be functionally tested as indicated in Table 4.2-7.
H.
Accident Monstonrm Instrumentation H.
Accident Morwtonne Instrumentation The limiting conditions for operation for the instrumentation Instrumentation shall be demonstrated operable by 4
that provides accident monitoring are given in Table 3.2-8.
performance of a channel check, channel calibration and functional test as indicated in Table 4.2-8, as applicable.
I.
4ky Emeroency Bus Undervoltane Tno I.
Not Used i
The limiting conditions for operation for the instrumentation that prevents damage to electrical equipment or circuits as a r
result of either a degraded or loss-of-voltage condition on the omergency electrical buses are given in Table 3.2-2.
1 Amendment No. 03, 2iS, 22?, 225 l.
53
@.2. BASES (cont'd)
Sumeiiiance Requirement 4.2.J requires that each remote shutdown transfer / isolation switch and control circuit be periodcally tested to demonstrate that it is capable of performing its intended functiort The reouirements of thissection apply to e penets listed in Table 3.2-10 and on penets 25 ASP-4, 25 ASP-5, and 66HV-38. This demonstration is performed from the' remote shutdown panel and locally, as appropdate. Thiswill ensure plant can be placed and maintained in a shutdown conditionfrom the rem n
I Three channels of the Reactor Vessel Water Level - High instrumentation are provided as input to a two-out-of-threeinitiation logic th fl w the main turbine. An everd involving excessive feedwater o results in a rising reactor vessel water level, which upon lt i a reaching the reactor vessel water level trip setpomt, resu s n trip of both feedwater pump turbines, and the main turbine.The feedwater further increase in the reactor vessel water level due tofeedwater flow. A tri from damage due to excessive water canyover.
Amendment No. 346., 225 60a
JAFNPP 3.2. BASES (cont'd)
Survedance Requirement 4.2.J requires that each remote shutdown transfer / isolation switch and control circuit be periodically tested to demonstrate that it is capable of performing its intended function. The requirements of this section apply to each remote shutdown control circuit on the panels listed in Table 3.2-10 and on panels 25 ASP-4, 25 ASP-5, and 66HV-30. This demonstration is performed from the' remote shutdown panel and locally, as appropriate. This
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will ensure that if the control room becomes iruwww=mible, the plant can be placed and maintained in a shutdown constion from the remote shutdown panel and the local control stations.
Three channels of the Reactor Vessel Water Level - High instrumentation are provided as input to a twoest-of-three initiation logic that trips the two feedwater pump turbines and the main turbine. An event involving excessive feedwater flow results in a rising reactor vessel water level, which upon reaching the reactor vessel water level trip setpoint, results in a trip of both feedwater pump turbines, and the main turbine.
i The feedwater pump turbine trip under these constions limits further increase in the reactor vessel water level due to feedwater flow. A trip of the main turbine protects the turbino from damage due to excessive water canyover, l
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Amendment No, g46., 225 g
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JAFNPP TABLE 32-6 FEEDWATER PUtr TURBINE Als MAIN TURBIPE TRIP INSTRUMENTATION REQUlfERIENTS 1
Moimum Number of Operable instrument Channels (Notes 1 & 2)
Trip Function Trip Level Setting Applicable Modes 3
Reactor Vessel Water Level-High s 222.5 inches Thermal Power a 25% RTP above TAF NOTES FOR TABLE 3.2-6
- 1. There shall be three operable instrument channels, except as provided for below-
- a. With one less than the required minimum number of operable instrument channels, either restore the inoperable iristrument i
channel to operable status, or place the inoperable instrument channel in the tripped condition, within 7 days. Othenmse, reduce reactor power to less than 25% rated thermal power withm the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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- b. With two or more channels less than the required minimum number of operable instrument channels, restore the feedwater I
pump turbine and main turbine trip capability withm 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Othenuse, reduce reactor power to less than 25% rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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- 2. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Umiting Conditions for Operation and required actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Trip Function maintains feedwater pump turbine and main turbine trip capability.
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Amendment No. '",10, 57, S7, ", i10,110, te: 225 76
JAFNPP TABLE 4.2-6 FEEDWATER PUMP TURBINE AND MAIN TURBINE TRIP INSTRUMENTATION TEST AND CALIBRATION REQUIREMENTS Instrument Channel Instrument Functional Logic System Functional CaHbration Frequency Instrument Check Test Frequency (Note 2)
Test Frequency Frequency Reactor Vessel Water Level-High Note 1 Once every 24 months Once every 24 months Daily NOTES FOR TABLE 4.2-6
- 1. Perform the instoment functional test:
- c. During each refueling outage, and
- b. Each time the plant is in cold shutdown for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 92 days.
- 2. This instrumerWation is exempt from the instrument channel functional test definition. The functional test will consist of injectog a sunulated electrical signal into the instrument chamel as close to the sensor as practicable.
e Amendment No. 225 84a
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