ML20106J738
| ML20106J738 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/11/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20106J740 | List: |
| References | |
| DPR-59-A-084 NUDOCS 8411010328 | |
| Download: ML20106J738 (8) | |
Text
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o UNITED STATES
[ 'i. 4.f 7; NUCLEAR REGULATOR.'/ COMMISSION k' "f/
C WASH NG TON. D. c. 20555 3Q N
,p 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. 84 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State l
of New York (the licensee) dated July 25, 1984, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,
, 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 (i) that the activities authorized by this amendment can be conducted without endangariro the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuaice of this amendment will not be inimical to the comon 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.
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.
OPR-59 is hereby amended to read as follows:
c 8411010328 841011 DR ADOCK 05000333 PDR
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
84, 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.
FOR THE NUCLEAR -REGULATORY COMMISSION j
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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 11, 1984
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ATTACHMENT TO LICENSE AMENDMENT N0. 84 FACILITY OPERATING LICENSE N0. DPR-59 DOCKET N0. 50 333-I Revise the Appendix "A" Technical Specifications as follows:
, Remove Insert l
66 66 i
67 67 68 68 l
69 69 f
119
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JAFilPP TABLE 3.2-2 INSTRUt1Ef3TATIOt1 TIIAT I!3ITIATES OR CONTROLS T!!E CORE At3D CONTAIt#4EtIT COOLING SYSTEMS
!!inimum No.
Total of Operable Number of Instru-Instrument ment Channels Pro-Item Channels Per vided by Design For No.
Trip System (1)
Trip Function Trip Level Setting Both Trip Systems Remarks 1
2
~ Reactor Low-Low
> -38 in. indicated 4 IIFCI & RCIC Initiates llPCI, Water Iavel 1evel (2L126.5'in.
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above the top of active fuel)
' 2 2
Reactor Low-Low-
> -146.5 in. indicated 4 Core Spray & RilR Initiates Core Sprayo Low Water Level
, level ( );18 in.
Instrument Channels LPCI, and' Emergency above the top of Diesel Generators.
active fuel) 4 ADS Instrument Initiates ADS in Channels conjunction with confirmatory low
, level, 120 second time delay and LPCI or Core Spray pump discharge pressure interlock i f not inhibited by ADS override switches.
3 2
Reactor liigh Water
(+58 in. indicated 2 Inst. Channels Trips llPCI and RCIC Level l'evel ($[ 222.5 in.
Turbines.
l above the top of active fuel) 4 1
Reactor Low Level
)+352 in, above 2 Inst. Channels Prevents inadvertent (inside shroud)
" vessel zero ( )> 0 in.
peration of containo above the top of ment spray during activo_ fuel) accident condition.
A m..n <inm a No. P(. 1.f. nd 84 66
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JAFt3PP TABLE 3.2-2 (Cont'd)
ItiSTRtir4Et3TATIOt3 TilAT IllITIATES OR CONTROLS Tile CORE At3D COllTAItiMEtiT COOLIt1G SYSTEMS Minimum tio.
Total of Operable 13 umber of Instru-Instrument ment Channels Pro-Item Channels Per vided by Design for tio.
Trip System (1)
Trip Function Trip Level Setting Both Trip Systems Remarks 5
2 containment liigh l < p < 2.7 psig 4 Inst. Channels Prevents inadvertent Pressure operation of contain-ment spray during accident condition.
6 1
Confirmatory Low 212.5 in. indicated 2 Inst. Channels ADS Permissive in Level level (2; 177 in, conjunction with above the top of Reactor Low-Low-Low active fuel)
Water Level.
7 2
Iligh Drywell
< 2.7 psig ilPCI Inst. Channels Irritiates Core Spray Pressure L1CI,IIPCI.& SGTS.
5 8
2 Reactor Low Pres-2t450 psig 4 Inst. Channels Permissive for opening sure Core Spray and LPCI Admission valves.
Arnendment 130. JM f(g, 84 67
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JAFNPP TABLE 3.2-2 (Cont'd)
It3STRUMEt3TATIOtt TilAT It3ITIATES OR CONTROLS TIIE CORE At1D CONTAINME!1T COOLING SYSTEMS
-)
Minimum No.
Total of Operable ilumber of Instru-Instrument ment Channels Pro-
'I Item Channels Per vided by Design for
-1 tio.
Trip System (1)
Trip Function Trip Level Setting Both Trip Systems Remarks 9
1 Reactor Low Pres-50.5 p $ 75 psig 2 Inst. Channels In conjunction with sure ICIS signal permits closure of RilR (LPCI injection valves, 10 l
1 i
11 TilIS ITEM INTEtiTIONALLY BLAllK
.j 12 1
Core Spray Pump 11 + 0.6 sec.
1 Inst. Channel
. Initiates starting 1
(See Note 3)
Start Timer of core spray pumps.
(each loop)
(each loop)
Amendment tio. }8',,44f, 84 68 Q
s JARIPP TABLE 3.2-2 (Cont'd)
It!STRUMEtITATIOri TilAT IllITIATES OR COtITROLS Tile CORE At3D COllTAItIME!IT COOLItIG SYSTEt1S Minimum tio.
Total of Operable fiumber of Instru-Ins trument ment Channels Pro-Item Channels Per vided by Design for flo.
Trip System (1)
Trip Function Trip Level Setting Both Trip Systems Remarks 13 1
RilR Purp Start Timer (See flote 3) 1s t Pump (A Loop) 1.0 + 0.5 (-) O sec.
1 Inst. Channel Starts 1st Pump (A Lo ist Pump (B Loop) 1.0 + 0.5 (-) O sec.
1 Inst. Channel Starts 1st Pump (B Lo 2nd Pump (A Loop) 6.0 j; 0.5 sec.
1 Inst. Channel Starts 2nd Pump (A Lo 2nd Pump (B Loop) 6.0 f;0.5 sec.
1 Inst. Channel Starts 2nd Pump (B Lo 14 1
Auto Blowdown Timer 120 sec f;5 sec.
2 Inst. Channels Initiates ADS, in conjunction with Low-Low-Low Reactor Water I
Level, and LPCI or Core Spray Pump dis-charge pressure inter lock, if not inhibite I
by ADS override switches.
15 2
RIIR ( LPCI) Pump 125 psig j; 20 psig 4 Inst. Channels Defers ADS actuation Discharge Pressure pending confirmation Interlock of low pressure core cooling system opera-tion.
Amendment tio.,M %,8, 84 69
m.
3.5 (con t'd )
JAFt3PP 4.5 1 cont'd)
D.
Automatic Depressurization System D. Automatic Depressurization System (ADS)
(ADS) 1.
The ADS shall be operable whenever 1.
Surveillance of the Automatic the reactor pressure is greater Depressurization System shall than 100 psig, and irradiated fuel be performed during each operating is in the reactor vessel and prior-cycle as follows:
to reactor startup from a cold condition, except as specified a.
A simulated automatic initiation below which opens all pilot valves.
a.
From and after the date b.
Manually open each relief / safety that one of the seven valve while bypassing steam to relief / safety valves of tha condenser and observe a 2 1034 the ADS is made or found closure of the turbine bypass to be inoperable for any valves, to verify that the reason.while it is required, relief / safety valve has opened.
continued reactor operation is permissible only during c.
A simulated automatic initiation the succeeding 30 days unless which is inhibited by the override repairs are made and provided switches.
that during such time the IIPCI System is operable, b.
From the time that more than one of the seven relief / safety
?
valves of the ADS are made or found to be inoperable for any reason, continued reactor opera-tion is permissible during the succeeding'24 hrs. unless repairs 4
are made and provided, that Amendment :.c.,,;T 84 119
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