ML20042F955
| ML20042F955 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/07/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042F956 | List: |
| References | |
| NUDOCS 9005100221 | |
| Download: ML20042F955 (9) | |
Text
-
l'
- 2 6
sa nta
-((
'o,,
UNITED STATES b
g NUCLEAR REGULATORY COMMISSION
'.*g
- [t g
WASHINGTON, D C. 20555
~
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL, DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY 0PERATING LICENSE i
Amendment No. 29 License No NPF-58 i
1..
TheNuclearRegulatoryCommission(theCommission)hasfoundthat:
A.
The application for amendment by The Cleveland Electric 1110 min-ating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania ~ Power Company, and Toledo Edison Company (the licensees)-
dated May 20, 1988 as supplemented November'27, 1989 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 defer.se 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. NPF-58 is hereby amended to read as follows:
$$0N00$bk f>b $0 P
t 1
(2) Technical Specifications The Technical Specifications-contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 29 are hereby incorporated into this license. The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION o
John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7, 1990 t
I s
i
ATTACHMENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are
.provided to maintain document completeness.
Remove Insert 3/4 3-5 3/4 3-5 3/4 3-46 3/4 3-46 B 2-9 B 2-9 B 2-10 B 2-10 1
l l
l.
1 l
l
1 TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM-!NSTRUMENTATION 1
TABLE NOTATIONS
. a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for
(
required surveillance without placing the trip system in the tripped condition provided at least one OPiCABLE channel in the same trip system is monitoring that parameter.
(b) Unless adequate shutdown margin has been demonstrated per Specifica-tion 3.1.1 and the "one-rod-out" Refuel position interlock has been-demonstrated OPERABLE per Specification 3.9.1, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn."
(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.
(d) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
(e) This function shall be automatically bypassed when the reactor mode switch is not in the Ron position.
(f) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required.
{
(g) With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(h) This function is automatically bypassed when turbine first stage pressure is less than the value of turbine first stage pressure corresponding to 40%** of RATED THERMAL POWER.
3 i
- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
- The Turbine First Stage Pressure Bypass Setpoints and corresponding AllowableValuesareadjustedbasedonFeedwatertemperatures(see3/4.2.2 for-definitionofAT). The Setpoints and Allowable Values for various ATs are as follows:
T(*F)
Setpoint (psig)
Allowable Value (psig) 0=T
< 212
< 218 0<
AT < 50 7 190 7 196 50 < AT c 100 7 168 7 174 100 < AT < 170 E146 i152 PERRY - UNIT 1 3/4 3-5 Amendment No. 29 l
TABLE.3.3.1-2 og
= REACTOR PROTECTION SYSTEM RESPONSE TIMES 4
e.5 FUNCTIONAL UNIT RESPONSE TIME (Seconds)
-e w
1.
a.
Neutron Flux - High NA b.
Inoperative NA 2.
Average Power Range Monitor *:
a.
Neutron Flux - High, Setdown NA b.
Flow Biased Simulatcd Thermal Power - High
< 0.09**
l c.
Neutron Flux - High
( 0.09 d.
Inoperative NA i
3.
Reactor Vessel Steam Dome Pressure - High
< 0.35 w
4.
Reactor Vessel Water Level - Low, Level 3 7 1.05 1
5.
Reactor Vessel Water Level - High, Level 8 7 1.05 i
w 6.
Main Steam Line Isolation Valve - Closure I 0.06 E
7.
Main Steam Line Radiation - High NA 8.
Drywell Pressure - Hign NA 9.
Scram Discharge Volume Water Level - High NA
- 10. Turbine Stop Valve - Closure
- 11. Turbine Control Valve Fast Closure,' Valve Trip System
-< 0.06 Oil Pressure - Low
< 0.07#
12.
Reactor Mode Switch Shutdown Position NA l
- 13. Manual Scram NA
- Neutron detectors are exempt from response time testing.
Response tis.a shall be measured l
from the detector output or from the input of the first electronic component in the channel.
- Not including simulated thermal power time constant, 6 i 0.6 seconds.
- Measured from start of turbine control valve fast closure.
e-m v
e
~
p-w s,
r
-+,e
+
4
v g
L INSTRUMENTATION l
SURVEILLANCE REQUIREMENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4,3.4.2.1-1.
4.3.4.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.4.2.3 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.4.2-3 shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least the logic of one type of channel input, turbine control valve fast closure or L
turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months.
The measured time shall be added to the most recent breaker arc suppression time and the resulting END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be verified to be within its limits.
4.3.4.2.4 The time interval necessary for breaker are suppression from energi-zation of the recirculation pump circuit breaker trip coil shall be measured at least once per 60 months.
PERRY - UNIT 1 3/4 3-45
TABLE 3.3.4.2-1 M
END-DF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION c-5
' MINIMUM
]
TRIP FUNCTION-OPERA 8LECHANNEg}
PER TRIP SYSTEM 1.
Turbine Stop Valve - Closure 2(b)-
2.
Turbino Control Valve - Fast Closure 2(b)
(a)A trip system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required serve 111ance provided that the other trip system is OPERABLE.
w}
(b)This function is automatically bypassed when turbine first stage pressure is less then the value of turbine first stage pressure corresponding to 40X* of RATED THERRAI. POWER.
w
- The TurM ne First Stage Pressure Bypass Setpoints and corresponding Allowable Values are adjusted based on feedwater temperatures (su 3/4.2.2 for definition of AT). The Setpoints and Allowable Values for various aTs are as folin s:
T(*F)
Setpoint (psig) 0=T Allowable Value (psig)
< 212
- < 218 E
O < AT < 50 7 190 7 196 50 < AT < 100 7 168 7 174
.[
100 < AT i 170 1146
{152 p
a
. ^
r 2..
a u
e--
.. mm
.--.a-:.%
w,-.-
LIMITINGSAFETYSY)TEMSETTINGS I
BASES i
REACTOR PROYECTION SYSTEM INSTRUMENTATION SETPOINTS (Continue 4.
Drywell Pressure-Hich High pressure in the drywell could indicate a break in the primary pressure i
boundary systems.
The reactor is tripped in order to minimize the possibility of fuel damage and reduce the amount of energy being added to the coolant and to the primary containment.
1 without causing spurious trips.The trip setting was selected as low as possible 9.
Scram Discharoe Volume Water Level-High The scram discharge volume receives the water dis the control rod drive pistons during a reactor scram. placed by the motion of Should this volume fill up to a point where there is insufficient volume to accept the displaced water at pressures below 65 psig, control rod insertion would be hindered. The reac-i tot is therefore tripped when the water level has reached a point high enough to indicate that it is indeed filling up, but the volume is still great enough to accommodate the water from the movement of the rods at pressures below 65 psig when they are tripped.
The trip setpoint for each scram discharge volume is equivalent to a contained volume of approximately 24 gallons of water.
10.
Turbine Stop Valve-Closure The turbine stop valve closure trip anticipates the pressure, neutron flux, and heat flux increasts that would result from closure of the stop valves.
With a trip setting of 5% of valve closure from full open, the resultant increase in heat flux is such that adequate thermal margins are maintained during the worst case transient.
As indicated in Table 3.3.1-1, this function is automatically bypassed below the turbine first stage pressure value equivalent to thermal-power less than 40% of RATED THERMAL POWER.
The automatic bypass setpoint is feedwater temperature dependent due to the i
subcooling changes that affect the turbine first stage pressure - reactor power i
i relationship.
For RATED THERMAL POWER operation with feedwater temperature greater than or equal to 420*F, an allowable value of 218 psig turbine first l
stage pressure is providau for the bypass function.
This setpoint is also applicable to operation at less than RATED 1HERMAL POWER with the correspond-ingly lower feedwater temperature. The allowable value is reduced as defined in Table 3.3.1-1 for RATED THERMAL POWER operation with a feedwater temperature between 370'F and t20'F; 370*F and 320*F; and 320*F and 250'F, respectively.
Similarly, the reduced setpoint is applicable to operation at less than RATED THERMAL POWER with the correspondingly lower feedwater temperature.
11.
Turbine Control Valve Fast Closure, Trip Oil Pressure-Low The turbine control valve fast closure trip anticipates the pressure, neutron flux, and heat flux increase that could result from fast closure of the PERRY - UNIT 1 B 2-9 Amendment No. 29
i
-LIMITING SAFETY SYSTEM SETTING SASES REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS (Continued) turbine control valves due to load rejection with or without coincident failure of the turbine bypass valves.
The Reactor Protection System initiates a trip when fast closure of the control valves is initiated by the fast acting sole-J noid valves and in less than 20 milliseconds after the start of control valve fast closure. This is achieved by the action of the fast acting solenoid valves in rapidly reducing hydraulic tri valve octuator disc dump valves. p oil pressure at the main turbine control This loss of pressure is sensed by pressure switches whose contacts form the one-out-of-two twice logic input to the Reactor Protection System.
This trip setting, a slower closure time, and a different valve characteristic from that of the turbine stop valve, combine to produce transients which are very similar to that for the stop valve.
Relevant tran-sient analyses are discussed in Section 15.2.2 of the Final Safety Analysis j
Report.
As with the Turbine Stop Valve-Closure, this function is also bypassed below 40% of RATED THERMAL POWER. The basis for the bypass setpoint and reduction of the setpoint due to reduced feedwater temperatures is identical to that described for the Turbine Stop Valve-Closure.
12.
Reactor Mode Switch Shutdown Position The reactor mode switch Shutdown position provides additional manual reactor trip capability.
13.
The Manual. Scram provides manual reactor trip capability. The manual scram function is composed of four push button switches in a one-out-of-two taken twice logic.
l i
PERRY - UNIT 1 8 2-10 Amendment No. 29
.. _ _