ML20204H483
| ML20204H483 | |
| 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 | |
| ML20204H488 | List: |
| References | |
| DPR-59-A-107 NUDOCS 8703270023 | |
| Download: ML20204H483 (8) | |
Text
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UNITED STATES j/ '
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'Fj NUC-LEAR REGULATORY COMMISSION 3,,
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00WER AUTHORITY OF THE STATE OF f1EW YORK DOCKET N0. 50-333 JAf1ES A. FITZPATRICK NUCLEAR POWER PLAfiT AMEhDMENT TO FACILITY OPERATING LICENSE Amendment No.107 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 4,1986, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,
, 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 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:
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g(2) -Technical Specifications s
.The Technical Specifications contained in, Appendices A and B, as revised through Amendment No. --107, are hereby incorporated;in -the.
license. The licensee shall operate-the. facility in accordar.ce
.with the. Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY ~COMMI S ON
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Daniel R. Muller, Director BWR Project Directorate *2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications l~
Date of Issuance: Marc'h 20, 1987 i
e AlTAChMENT TO LICENSE AMENDP. elf NO. 107 FfACILITYOPERATINGLICENSENODPR-59 DOCKET NO. 50-333 P.eplace the following peces of the Appendix A Technical Specificaticns with the enclosed pges. The revised areas are indicatec by marginel lines.
Peges 117 118 121 128 129 l
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o-JAFNPP 3.5 (Cont'd) 4.5 (Cont'd)
DELETED C.
HIGH PRESSURE COOLANT INJECTION'(HPCI' SYSTEM)
C.
HIGH PRESSURE COOLANT INJECTION (HPCI SYSTEM)
Surveillance, of HPCI System shall be performed as follows provided a
reactor steam supply _ is -
available.
If steam is not available at the time the surveillance-test, is. scheduled to = be Y'
performed,-the test shall be perforged within 10 days of continuous operation from the,. time steam becomes available.
1.
The HPCI System shall be operable whenever
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HPCI System \\ testing shall be as specified in-the reactor pressure is greater than 150 4.5.A.l.a,.
b, c,
d, f, and g except that the psig and reactor coolant temperature is HPCI pump shall deliver at ileast 4,250 gpm I
greater than 212*F and irradiated fuel is in against a system head correspondin9 to a the reactor
- vessel, except as specified reactor. vessel pressure of,1,120 psig to 150 below:
psig.
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Amendment g, #f 107
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is determined that the HPCI subsystem
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When it
"") # From and af ter the date thit lWSPCI System,/
is inoperable the. RCIC, the LPCI subsystemi a.
is ~ made or found to, be inoperable-f5r any reason, contii.aed reactor operation. is per-4 both core spray subsystems,
'and
.the.
ADS missible only during the succeeding 7 days subsystem.
actuation-logic shal1J be demonstrated to be oper6ble immediately, unless such system is sooner made ' operable, provided that during such.'7 days ' all active.
The RCIC syster "dnd ADS subsystem : logic shall be demo 6strated to be operable f daily components of'the Automatic Depressurization thereafter.-
System, the Corp Spray System, ' LPCI System,
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and Reactor Core Isolation Cooling System-
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" are operable.
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If the requirements of.3.5.C cannot be met, the reactor shall be placed in the. cold 7'
condition and pres'sure less than 150 psig within 24 hrs.
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2.
Low power physics testing and reac' tor operator training shall be permitted with reactoT' coolant temperature f 212*F with an irioperable com-ponent(s) 'as specified in 3.5.C.1 above.
l Amendment No. # 107 118
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-';y-JAFNPP 4.5 (Cent'd)
V 3.5 (Cont'd)
Reactor Core Isolation Cooling (RCIC) System E.
Reactor Core Isolation Coolle.t (RCIC) System E.
1.
The RCIC System shall be operable whenever 1.
RCIC System testing shall be performed as there is irradiated fuel in the reactor follows provided a reactor steam supply is vessel and the reactor pressure is greater available.
If steam is not available at the than 150 psig and reactor coolant tempera-time the surveillance test is scheduled to ture is greater than 212*F except from the be performed, the test shall be performed time that the RCIC System is made or found within ten days of continuous operation from to be inoperable for any reason, continued the time steam becomes available.
reactor power operation is permissible during the succeeding 7 days unless the Item Frequency system is made operable earlier provided Once/ operating that during these 7 days the HPCI System is a.
Simulated Automatic cycle operable.
Actuation 2.
If the r equi rements of 3.5.E cannot be me t,
x Test the reactor shall be placed in the ccid condition and pressure less than 150 psig
- b. ~ Pump Operability once/ month within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
Motor Operated Once/ month
_ Valve Operability 3.
Low power physics testing and reactor opera-tor' training shall-be permitted with inoper-R.le components as specified in 3.5.E.2 d.
Flow Rate Once/3 months
- above, provided that reactor coolant
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Testable Tested for opera-temperature isy,212*F.
Check Valves bility any time the reactor is in the cold condition exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
if operability tests have not been performed during the pre-ceding 31 days.
omendment jr,107 121 I
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y JAFNPP 3.5 BASES (cont'd)
C.
High Pressure Coolant Injection (HPCI) System enable the Core Spray or LPCI Systems.to provide pro-tection against the small pipe break in the event of The High Pressure Coolant Injection System is llPCI. f ailure, by depressurizing _ the reactor vessel provided to adequately cool the core for all pipe rapidly enough to actuate the Core Spray.or LPCI breaks smaller than those for which the LPCI or Systems.
The core spray and/or LPCI provide suffi-Core. Spray Systems can protect '.se core.
cient flow of coolant to limit fuel clad temperatures to well below clad fragmentation and to assure that' The HPCI meets this requirement without the use core geometry remains intact.
of a-c electrical power.
For the pipe breaks for which the HPCI is intended to function, the core Redundancy has been provided in the_ automatic pressure never uncovers and is continuously cooled and relief function in that only six of the seven val'ves thus no clad damage occurs.
Refer-to Section are required to operate.
Loss of one of the relief 6.5.3 of the FSAR.
valve.1 does not materially affect the pressure re-lieving capability, and therefore_a thirty-day repair Low power physics testing and reactor operator period is specified.
Ioss of more than one relief training with inoperable component (s) will be valve significantly reduces the pressure relief capa-conducted only when the HPCI System is-not bility, and thus.a 24-hr. repair period is specified.
required, ( reactor coolant ' temperaturen 212*F and coolant pressure i 150 psig).
If the plant Low power physics testing and reactor operator paramet~ers are below the point where the HPCI training with inoperable components will be conducted System is required, physics testing and operator only when that component or system is not required, training will not place the plant in an unsafe (reactor coolant ~ temperature n 212*F and reactor condition, essel vented.or the reactor vessel-head removed).
-. i t h the reactor coolant temperature f 212*F and the Operability of the HPCI System is required only Reactor vessel vented or the when reactor pressure is greater than 150 psig and reactor coolant temperature is greater than 212*F because core spray and low pressure coolant injection can protect the core for any size pipe break at low pressure.
D.
Automatic Depressurization System (ADS)
The relief valves of the ADS are a backup to the HPCI subsystem. They l
Amendment No. 107 128
1 JAFNPP 3.5 BASES (cont'd) vessel head off the LPCI and Core Spray Systems testing and operator training will not place the will perform their designed aafety_ function plant in an unsafe condition, without the help of the ADS.
Operability of the RCIC System is required only E.
Reactor Core Isolation. Cooling (RCIC) System when reactor pressure is' greater than 150 psig and reactor coolant temperature is greater than The RCIC is designed to provide makeup to the 212*F because core spray and low pressure coolant Reactor Coolant System as a planned operation for injection can protect the core for any size pipe periods when the normal heat sink is unavailable, break at low pressure.
The RCIC also serves as redundant makeup system on total loss of all offsite power in the event F.
Minimum Emergency Core and Containment Cooling that HPCI is unavailable.
In all other System Availability postulated accidents and transients, the ADS provides redundancy for the HPCI.
Based on this The purpose of Specification 4.5.D is to assure a-and judgements on the reliability of the HPCI minimum of emergency core cooling equipment ' is system, an allowable repair time of 7 days is available at all times.
If, for example, one core specified.
Immediate and daily demonstrations of spray were out of service and the emergency bus HPCI operability during RCIC outage is considered which powered the opposite core spray were out of adequate based on judgement and practicality.
service, only two RHR Pumps would be available.
Likewise, if two RHR pumps were out of service Low power physics testing and reactor operator and two RHR on the opposite side were also out of training with inoperable components will be con-service, no containment cooling would be avail-ducted only when the RCIC System is not required, able.
It is during refueling outages that major (reactor coolant temperature $ 212*F and coolant maintenance is performed and during such time pressure i 150 psig).
If the plant parameters that all low pressure core cooling systems may be are below the point where the RCIC System is out of service.
This specification provides that required, physics should this occur, no work will be performed on the Reacto Coolant System which could lead to draining the vessel.
This work would include work on certain control rod drive components and Reactor Recirculation System.
Thus, the specifi-cation precludes the events which could require core cooling.
Specification 3.9 must also be consulted to determine other Amendment No J4"107 129