ML20040G308
| ML20040G308 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/29/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20040G309 | List: |
| References | |
| DPR-59-A-062 NUDOCS 8202120148 | |
| Download: ML20040G308 (15) | |
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UNITED ST'ATES j
y NUCLEAR REGULATORY COMMISSION i
j WASHINGTON, D. C. 20065 e
49*****,o POWE't AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT' AMENDMENT TO FAC'ILITY OPERATING LICENSE Amendment No 62 l
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 of New York (the licensee) dated January 6,1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (1) 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
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conducted in compliance with the Comission's regulations; D.
The issuaned of this amen'dment 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 1
51 of the Comission's regulations and all applicable requirements have been satisfied.
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8202120148 820129 I
DR ADOCK 05000 L
- 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, 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 Domenic B. Vassallo, Thief' Operating Reactors Branch Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 29, 1982 S
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET N01'50-333 Replace the following pages of _the Appendix."A" Technical-Specifications with the enclosed pages:
Remove Insert 43 43
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44 44 45 45 45a 46 46 47-47 72 72 73 73 81 81 89'-
89 89a 89a 96 96 o
l l
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JAFNPP TABLE 3.1-1 (cont'd)
REACTOR PRtin2 TION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT NOTES OF TABLE 3.1-1 (cont'd)
C.
High Flux IRM Scram Discharge' Instrument Volume High Ievel when any control rod in a control cell cont'aining fuel I
D.
is not fully inserted E.
APRM 15% Power Trip containment integrity is not required.,
Not required.to be operable when priinary 7.
Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
8.
high.
W e APRM downscale trip is automatically bypassed when the IRM Instrumentation is operable and not 9.
11 LPRM An APRM will be considered operable if there are at least 2 LPRMinputs per level and at least 10.
/
1 inputsof the riormal couplement.
11.
See Section 2.1.A,1.
i This equation will be uced in the event of operation with a maximum fraction, of limiting power dens ty 12.
(MFLPD) greater than the fraction of rated power (FRP).
where
- Fraction of rated thermal power (2436 MWt).
FRP i
is 18.3
- Maximum fraction of limiting power density where the limiting power dens ty i
KW/ft for 7x7 fuel and.13.4 MW/ft for 8x8, Bx8R and P8x8R fuel.
%e ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less.
than the design value of 1.0, in which case the actual operating value will be used' j'
/['
6
- Icop,decirculation flow in percent of rated (rated is 34.2 x lO 'lb/hr)
W 4
- Scram setting in percent of initial i
loop l
%e Average Power Range Monitor scram function is varied (Figure 1.1-1) as a function of recirculat on 2.1.A.l.c.
The trip setting of this function must be maintained in accordance with Specification.
13.
flow (W).
i 43 f
Amendmerit No.,M, 62 e
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JAFNPP l
Table 4.1-l' REACTOR PRCyrECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS
' MINIMUM FUNCTIOt1AL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2)
Functional Test Minimum Frequency (3)
A Place Mode Switch in Shutdown Each refueling outage.
Mode Switch in shutdown A
Trip Channel and Alarm Every 3 months.
Manual Scram RPS Channel Test Switch A
Trip Channel and Alarm Every refueling outage or 1
after channel maintenance.
C Trip Channel and, Alarm (4)
Once per week during re-IRM High Flux fueling or startup and r
j before each startup.
t C
Trip Channel and Alarm (4)
Once.per week during re-Inopekative fueling or startup and before each startup.
APRM B
Trip output Relays (4)
Once/ week.
High Flux B
Trip output Relays (4)
Once/ week.
Inoperative Trip output Relays (4)
Once/ week.
Downscale B
Flow Bias B
Calibrate Flow Bias Signal (4)
Once/ month. (1)
High Flux in Startup or Refuel C
Trip Output Relays (4)
Once per week during refueling or startup and before each startup.
B Trip Channel'and Alarm (4)
Once/ month. (1) (Instrument check High Reactor Pressure once per day)
A Trip Channel and Alarm once/ month (1) f High Drywell Pressure Reactor Low Water Level (5)
A Trip Channel add Alarm Once/ month (1) e Once/ month and before each A
Trip Channel and Alarm 1
High Water Level in Scram startup (6), (7)
Discharge Instrument Volume Main Steam Line High Radiation B
Trip Channel and Alarm (4)
Once/ week.
44 Amendment'No. 4Q, 62
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JAFNPP Table 4.1-1 (cont'd)
REACTOR PROftA;rION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SArt.tr INSTRUMENT AND C Minimum Frequency (3)
Functional Test Group (2)
Once/ month. (1)
Trip' Channel and Alarm A
Main Steam Line Isolation Valve Closure Once/ month.
Trip Channel and Alarm A
Turbine Control Valve EllC Oil Pressure Every 3 months. (1)
A Trip Channel and Alarm Turbine First Stage Pressure Once/ month. (1)
Permissive Trip Channel and Alarm A
Turbine Stop Valve closure
)
Every 3 months.
Trip Channel and Alarm A
Reactor Pressure Permissive NOTES FOR TABLE 4.1-1 t may be made Initially once every month until acceptable failure rate data are available thereafter,a requesThe l
1.
t in an environment to the NBC to change the test frequency.
obtained from other boiling water reactors for which. the same design instrument opera es y
similar to that of JAFNPP.
i A description of the three groups is included in the Bases' of this'Specificat on.
2.
be operable or arc tripped.
FunctioAtl tests are not required on the part of the system that is not required to 3.
h ll be performed prior to If tests are missed on parts not required to be operable or are tripped, then they s a returning the system to an operable, status.
l; This instrument channel This instrumentation is exempted from the instrument channel test, definition. f h
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45 I
Amendment No.K 62 f
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- JAFNPP Table 4.1-1 (cont'd)
REACTOR PRCYTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MI' IMUM FUNCTIONAL TSST FREQUENCIES FOR' SAFETf' INSTRUMENT AN H
e I
.NCyrES FOR TABLE 4.1-1 (cont'd) h ill be The water level in the reactor vessel will be perturbed and the corresponding lev 5.
monitored.-
i program.
last Functional test of the instruments before each startup is required only if a scram has becurred since the 6.
functional test or calibration.
h The functional test shall be performed utilizing a water column or similar device to provide assurance t at damage. to a float or other portions of the float assembly will be detected.
7.
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Amendment No. g, 62 i
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JAFNPP Table 4.1-2 4
REACTOR PROTECTION SYSTEM (SCRAM)-INSTRUMENT CALIBRATION i
MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTFCTION INSTRUMENT CHANNEL Minimum Frequency Once/ week Group (1)
Calibration (4)
Instrument Channel-Maximum frequency once/ week C
Comparison to APRM on I
IRM High Flux Controlled Shutdowns 1
D Heat Balance Daily APRM High Flux t
Internal Power and Every refueling outage Dutput' Signal B
Fluw Bias Signal Flow Test with Stan-dard Pressure Source 1
l Every 1000 effective full l
B TIP System Traverse LPRM Signal power hours
{
l Once/ operating cycle 1
B Standard Pressure High Reactor Pressure Source l
l Standard Pressure Every 3 months A
High Drywell Pressure Source s
A Pressure Standard Every 3 months' Reactor Low Water sevel
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Water Cclumn, Note (6)
Once/ operating cycle, Note (6)
A High Water level in Sc' ram Dis-l charge Instrument Volume f
A Note (5)
Note (5) -
l Main Steam Line Isolation valve I
- I Closure B
Standard Current Every 3 months,
Main Steam Line High Radiation Source (3) t.
Standard Pressure Every 6 months A
p Turbine Plant Stage Pressure Source
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Permissive Once/ operating cycle A
Standard Pressure l
Turbine Control Valve Past Closure 7
Source Oil Pressure Trip 46 I
Amendment No. (2, 43, 62
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JAFNPP Table 4.1-2 (cont'd) l INSTRUMENT CALIBRATION _
REACTOR PRun,CTION SYSTEM (SCRAM)
NELS MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTBCTION INS Minimum Frequency (2)
Group (1)
Calibration (4)
Instrument Channel Note (5)
Note (5)
A Turbine Stop Valve Closure Every 6 months A
Standard Pressure Reactor Pressure Permissive Source NOTES FOR TABLE 4.1-2_
j i
A description of three groups is included in the Bases of this Specificat on.
i 1.
i d to be operable, or Calibration test is not required on the part of the system that is not requ re
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is tripped, but is required prior to return to service.
2.
Calibration using a radiation source
'the current source provides an instranent channel alignment.
J 3.
shall be made each refueling outage.-
il'1 be checked once per Response time is not a part of the routine instrument channel test but v I
4.
operating cycle, f ling outages.
Actuation of these switches by normal means will be performed during the re ue i'
5.
i to provide assurance that Calibration shall be performed utilizing a water column or similar dev ceportions of t i
6.
damage to a float or other i
47, Amendment No. 40, 62 9
JAFNPP TABLE 3.2-3 INSTRUMENTATION THAT INITIATES CONTROL ROD BLO.CKS o
Minimum No.
Total Number of of Operable Trip Level Setting Instrument Channels Action Instrument Instrument Provided by Design Channele Per for Both Channels Trip System.
6 Inst. Channels (1)
APRM Upscale (Flow Biased)
S 5,(0.66W+42%)x FRP
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2' MFLPD 1
6 Inst. Channels (1)
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2 APRM Upscale (Start-up 3,12%
Mode) 6 Inst. Channels (1) 2 APRM Downscale 3,2.5 indicated on scale 2 Inst. Channels (1) 1 (6)
Rod Block Monitor S j:, 0.66W+K (8)
(Flow Biased) i 2 Inst. Channels (1) 1 (6)
Ikx1 Block Monitor 3,2.' indicated on scale Downscale 8 Inst. Channels (1) 3 IRM Downscale (2) 3,2% of full scale 8 Insc. Channels (1) i IRM Detector not in (7) 3 Start-up Position 8 Inst. Channels (1) 3 IRM Upscale 3,86.4% of full scale 2 - (4)
SRM Detector not in (3) 4 Inst. Channels (1) eI Start-up Position 1
5 counts / sec 4 Inst. Channels (1) fl 2 (4)(5) SRM Upscale
$10 1 Inst. Channel (9) (10) l I
i Scram Discharge Instrument j:,18 gallons 1
- j Volume fligh Water Level
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NOTES FOR TABLE 3.2-3 For the Start-up and Run positions of the Reactor M' ode Sel'ector Switch, there shall be two ' operable or l
1.
tripped trip systems for each function. The SRM and IRM blocks need not be operable in run mode, and 4
72 Amandment No. 49, 62
t JAFNPP TABLE 3.2-3 (Cont'd)
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INSTRUMENTATION THAT INITIATES CONTROL ROD BIOCKS NOTES FOR TABLE 3.2-3 From and after the time it is the APRM and RBM rod blocks need not be operable in start-up mode.found that the first colu for up to seven days provided that during that time the operable system is functionally tested launediately and. daily thereafter,.if this condition lasts longer than seven days, the s be tripped.
systems, the systems shall be tripped, s
IRM downscale is bypassed when it is 'on its lowest range.
2.
This function is bypassed when the count rate is > 100 cps.
3.
One of the four SRM inputs may be bypassed.
4.
H is SRM Function is bypassed when the IRM range switches are on range 8 or above.
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5.
% e trip is bypassed when the reactor power is,< 30s.
l 6.
@ is function is bypassed when the Mode Switch is placed in Run.
7.
S = Rod Block Monitor Setting in percent of initial.
6 lb/hr).
f 8.
W.= Icop becirculation flow in percent of rated,(rated loop recirculation flow is 34.2 x 10 K = Intercept values of 39%, 40s, 41% and 42% can be used with appropriate MCPR limits from f
Section 3.1.B.
and the reactor water temperature is less than 2120F,.the control 9.
When the reactor is suberiticalrod block is required to be operable only if any control rod in a control cell containing, fuel is not fully inserted.
When the control rod block function associated with scram discharge instrument volume high water level
'l is not operable when required to be operable, the trip system shall be tripped.
10.
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73 Amendment No. g, 62 t
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JAFNPP TABLE 4.2-3 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD DIDCKS ACTUATION Instrument Functional Test Calibration Instrument Check (9)
Ir.strument Channel (1)
(3)
Once/3 months once/ day
- 1) APRM - Downscale (1)' (3)
Once/3 months once/ day
- 2) APRM - Upscale (2)
(3)
(2)
(2)'
- 3) IRM
-Upscale
- 4) IRM - Downscale (2)
(3)
(2)
(2)
(1)
(3)
Once/3 months Once/ day l
5)
RBM - Upscale (1)
(3)
Once/3 months Once/ day l
- 6) RLM - Downscale (2)
(3)
(2)
(2)
- 7) ' SRM - Upscale (2)
(3)
(2)
- 8) SRM - Detector Not in Stattup Position (2)
(3)
(2)
- 9) IRM - Detector Not in Startup Position Once/ month (2)
Once/ operating Cycle (2)
N/A l
- 10) Scram Discharge Instrument volun.e - liigh water level Logic System Functional Test (4 ) (6)
Frequency once/6 months
- 1) System Logic Check 1
4.2-6 for the notes referred to herein.
i HOTE: See listing of notes following Table t
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81 Amendment No.y, 62
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4.3 (cont'd)
JAFNPP 3.3 (cont'd)
Each partially cn/ fully a.
Control rods which withdrawn operable control a.
cannot be soved with rod shall be exercised one control rod drive notch at least once each I
pressure shall be week when operating above 30 considered inoperable.
percent power.
In the event If a partially or fully power operation is continuing withdrawn control rod with three or more inoperable drive cannot be moved control rods, this test shall with drive or scram be performed at least once each pressure, the reactor day, when operating above 30 shall be brought to percent power.
the Cold shutdown con-dition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> The scram discharge volume drain b.
and shall not be started and vent valves shall be verified unless (1) investigation open.at least once per 31 days l
has demonstrated that the (these valves may be closed inter-mittently for testing under' admin-cause of the failure is 4
not a failed control rod istrative control).
drive mechanism collet A.second licensed operator l
housing, and (2) adequate c.
shutdown margin has been shall verify the conformance demonstrated as required to Specification 3.3.A.2'.d by Specification 4.3.A.
before a rod may be bypassed 4
in the Rod Sequence Control If investigation demonstrates System.
that the cause of control l
rod failure is a cracked d.
Once per week check status collet housing, or if this of pressure and level alaram possibility cannot be ruled for each accumulator.
9 out., the reactor shall-not l-be started until the affected J
control rod drive has been
- I replaced or repaired.
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89 Amendment No. )df, 62.
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When it is initially determined that l
e.
b.
'Ihe control rod a control rod is incapable of normal directional control insertion,.an atteapt to fully insert valves for. inoperable the control rod shall be made. If
' control rods shall be the control rod cannot be fully disarmed electrically.
inserted
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Control rods with shutdown margin test shall be made c.
scram times greater to demonetrate under this condition than those permitted that the core can be.made subcritical for any reactivity condition during by the remainder of the operating cycle Specification 3.3.C.3 are' inoperable, but with the analytically determined, if they can be highest worth control rod capable of inserted with control withdrawal, fully withdrawn, and all rod drive pressure other control rods capable of inser-they need not be tion fully inserted. If Specification disarmed 3.3.A.1 and 4.3.A.1 are met, reactor startup may proceed.
i d.
Control rods w'ith a f.
The scram discharge volume drain and failed " Full-in" or vent valves shall each be full travel
" Full-out" position cycled at least once per quarter.
switch may be bypassed in the Rod Sequence Control System and corisidered operable if the actual rod position is known. These rods must be moved in 4
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i 89a Amendment No.,M, 62 l i f
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i JAFNPP 4.3 (cont'd) 3.3 (cont'd)
At 8-week intervals,15 percent of 2.
i The average of the scram insertion the operable control rod drives shall 2.
times for the three fastest operable be scram timed above 950 psig. When-control rods of all groups of four ever such scram time measurements are control rods in a two-by-two array made, an evaluation shall be made to shall be no greater thans provide reasonable assurance that
(,
proper control rod drive performance Control Rod Average Scram l
Notch Position Insertion Time is being maintained.
Observed (Sec)
All control rods shall be determined 3.
. operable once each operating cycle 46' O.361 by demonstrating the scram discharge-0.977 38 volume drain and vent valves operable-2.112 24 when the scram test initiated by 3.76J placing the mode switch in the SHUTDOWN 04 position is performed as required by Table 4.1-1 and by verifying that the '
~ drain and vcnt valves Close within 80 seconds after a.
receipt of a signal for control rods to scram, and b.
Open when the scram signal is reset or the scram discharge instrument volume trip is bypassed.
9 96 Amendment No. pf, 62
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