ML20065R445
| ML20065R445 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/05/1994 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065R449 | List: |
| References | |
| NUDOCS 9405110226 | |
| Download: ML20065R445 (11) | |
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UNITED STATES 5I E
NUCLEAR REGULATORY COMMISSION k..v,/
WASHINGTON. D.C. 20555-0001 BOSTON EDISON COMPANY DOCKET N0. 50-293 PILGRIM NUCLEAR POWER STATION 3
AMENDMENT TO FACILITY OPERATING _11 CENSE Amendment No.152 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Boston Edison Company (the licensee) dated October 19, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations; B.
The facility will operate in conformity with the application, the i
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 j
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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:
9405110226 940505 PDR ADOCK 05000293 P
l
' Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.152, 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 its date of issuance and i
shall be implemented coincidental with the_ corresponding plant design change.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate 1-3 Division of Reactor _ Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 5, 1994
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ATTACHMENT TO LICENSE AMENDMENT NO. 152 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 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.
Remove Insert 2
2 3
3 27 27 29 29 30 30 i
)
32 32 35 35 38 38 I
l r,
- - - =.
o 1.0 DEFINITIONS (Cont'd)-
E.
Operable - Operability A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (i).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their-related support function (s).
F.
Operatina - Operating means that a system or component is performing its intended functions in its required manner.
G.
Immediate - Immediate means that the required action will be initiated as soon.as practicable considering the safe operation of the unit and the importance of the required action.
H.
Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1% design power.
1.
Hot Standby Condition - Hot standby condition means operation with coolant temperature greater than 212 F, system pressure less than 600 psig, the main steam isolation valves closed and the mode switch in startup.
J.
Cold Condition - Reactor coolant temperature equal to or less than 212 F.
i K.
Mode - The reactor Mode is that which is ~ established by the mode selector-switch.
The modes include shutdown, refuel, startup and run which are defined as follows:
1.
Startuo Mode - In this mode the reactor protection scram trip, initiated by main steam line isolation Amendment No. -64,152 2
l
=
l.0 DEFINITIONS (Cont'd) valve closure, is bypassed when reactor pressure is less than 600 psig, the low pressure main steam line isolation valve closure trip is bypassed, the reactor protection system is energized with IRM neutron monitoring system trips and control
(
rod withdrawal interlocks in service.
2.
Run Mode - In this mode the reactor system pressure is at or above 880 psig and the reactor protection system is energized with APRM protection and RBM interlocks in. service.
3.
Shutdown Mode - The reactor is in the shutdown mode.when the reactor mode switch is in the shutdown mode position and no j
core alterations are being performed.
(
a.
Hot Shutdown means conditions as above with. reactor
. coolant temperature greater than 212 F.
b.
Cold Shutdown means conditions as above with reactor coolant' temperature ' equal to or less than 212 F, 4.
Refuel Mode - The reactor is in the refuel mode when the mode
(
switch is in the refuel mode position.
When the mode switch is l
in the refuel position, the refueling interlocks are in l
service.
1 L.
Desian Power - Design power means a steady-state power level of 1998 thermal megawatts.
j M.
Primary Containment Intearity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:
1.
All manual containment isolation valves on lines connected to the reactor coolant system or containment which are not required to be open during accident conditions are closed.
2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
l 4.
All automatic primary containment isolation valves are operable l
or at least one containment isolation valve in each line having l
an inoperable valve shall be deactivated in the isolated condition.
5.
All containment isolation check valves are operable or at least l
one containment valve in each line having an inoperable valve is secured in the isolated position.
N.
Secondary Containment Intearity - Secondary containment integrity means that the reactor building is intact and the following conditions are met:
Amendment No. 113, 152 3
l
PNPS Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Operable Inst.
Modes in Which Function Channels per Trip Function Trip Level Setting Must Be Operable Action III i
Trip System (1)
Refuel (7) Startup/ Hot Run i
MinimumlAvail.
Standby 1
1 Mode Switch in Shutdown X
X X
A 1
1 Manual Scram X
X X
A t
IRM 3
4 High Flux
$120/125 of. full scale X
X (5)
A 3
4 Inoperative X
X (5)
A APRM 2
3 High Flux (15)
(17)
(17)
X A or B 2
3 Inoperative (13)-
X X(9)
X A or B 2
3.
High Flux (15%)
515% of Design' Power X
X (16)
A or 8 2
2 High Reactor Pressure
$1063.5 psig X(10)
X X
A 2
2
.High Drywell Pressure
$2.22 psig X(8)
X(8)
X A
2 2
Reactor Low Water Level 211.7 In. Indicated X
X X
A Level SDIV High Water Level:
538 Gallons X(2)
X X
A 2
2 East 2
2 West i
2 2
Main Steam Line High 57x Normal Full Power X
X X(18)
A or C
' Radiation Background (18) 4 4
Main Steam Line Isolation Valve Closure
$10% Valve Closure X(3)(6)
X(3)(6)
X(6)
A or C 2
2 Turbine Control Valve 2150 psig Control Oil Fast Closure Pressure at Acceleration Relay X(4)
X(4)
X(4)
A or D 4
4 Turbine Stop Valve
$10% Valve Closure X(4)
X(4)
X(4)
A or D Closure 15,-42;-86 117; 133,147, AW,152 27
' Amendment No.
5 7
s
NOTES FOR TABLE 3.1.1 (Cont'd) 2.
Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions of the reactor mode switch.
3.
Permissible to bypass when reactor pressure is $576 psig.
4.
Permissible to bypass when turbine first stage pressure is 1112 psig.
l S.
IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is subcritical, fuel is in the reactor vessel and the reactor water temperature is less than 212 F, only the following trip functions need to be operable:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge volume high level E.
Not required to be operable when primary containment integrity is not required.
9.
Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
- 10. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
- 11. Deleted
- 12. Deleted 13.. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% of the normal ' complement of LPRM's to an APRM.
- 14. Deleted
- 15. The APRM high flux trip level setting shall be as specified in the CORE OPERATING LIMITS REPORT, but shall in no case exceed 120% of rated thermal power.
- 17. The APRM flow biased high flux scram is bypassed when in the refuel or startup/ hot standby modes.
- 18. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of hydrogen injection with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the injection of hydrogen.
The background radiation level and associated trip setpoints may be adjusted based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen injection and prior to withdrawing control rods at reactor power levels below 20% rated power.
Amendment No. 6, 15, 27, 42, 86, 117, 118, 133, 147, FFF, 152 29
TABLE 4.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS Functional Test Minimum F i equen(/_{3)
Mode Switch in Shutdown Place Mode Switch in Shutdown Each Refueling th:tage j
Manual Scram Trip Channel and Alarm Every 3 Months
.RPS Channel Test Switch (5)
Trip Channel and Alarm Once per week i
i IRM High Flux Trip Channel and Alarm (4)
Once Per Week During Refueling and Before Each Start up Inoperative Trip Channel and Alarm Once Per Week During Refueling and Before Each Startup APRM High Flux Trip Output Relays (4)
Every 3 Months (7)
Inoperative Trip Output Relays (4)
Every 3 Months, Flow Bias Trip Output Relays (4)
Every 3 Months High Flux (15%)
Trip Output Relays (4)
Once Per Week During Refueling and Before Each Startup i
High Reactor Pressure Trip Channel and Alarm (4)
Every 3 Months 4
High Drywell Pressure Trip Channel and Alarm (4)
Every 3 Months Reactor Low Water level Trip Channel and Alarm (4)
Every 3 Months High Water Level in Scram Discharge Tanks Trip Channel and Alarm (4)
Every 3 Months I
Main Steam Line High Radiation Trip Channel and Alarm (4)
Every 3 Months Main Steam Line Isolation Valve Closure Trip Channel and Alarm Every 3 Months Turbine Control Valve Fast Closure Trip Channel and Alarm Every 3 Months Turbine First Stage Pressure Permissive Trip Channel and Alarm (4)
Every 3 Months Turbine Stop Valve Closure Trip Channel and Alarm Every 3 Months Reactor Pressure Permissive Trip Channel and Alarm (4)
Every 3 Months i
30 Amendment No. 79, 117, 147, 152 s
l TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Calibration Test (5)
Minimum Freauency (2)
IRM High Flux Comparison to APRM on Controlled Note (4)
Shutdowns Full Calibration Once per Operating Cycle APRM High Flux Output Signal Heat Balance Once every 3 Days Flow Bias Signal Calibrate Flow Comparator and At least Once Every Flow Bias Network 18 Months Calibrate Flow Bias Signal (1)
Every 3 Months LPRM Signal TIP System Traverse Every 1000 Effective Full Power Hours High Reactor Pressure Note (7)
Note (7)
High Drywell Pressure Note (7)
Note (7)
Reactor low Water Level Note (7)
Note (7)
High Water Level in Scram Discharge Tanks Note (7)
Note (7)
Main Steam Line Isolation Valve Closure Note (6)
Note (6)
Turbine First Stage Pressure Permissive Note (7)
Note (7)
Turbine Control Valve Fast Closure Standard Pressure Source Every 3 Months 1
Turbine Stop Valve Closure Note (6)
Note (6)
Reactor Pressure Permissive Note (7)
Note (7) 1 Amendment No.147, kVV,152 32
\\
3.1 BASES (Cont'd) j The requirement that the IRM's be inserted in the core when the APRM's read 2.5 indicated on the scale assures there is proper overlap in the neutron monitoring systems and thus, sufficient coverage is provided for all ranges of reactor operation.
The provision of an APRM scram at 115% design power in the Refuel and Startup/ Hot Standby modes and the backup IRM scram at $120/125 of full scale assures there is proper overlap in the Neutron Monitoring Systems arid thus, sufficient coverage is provided for all ranges cf reactor i
operation.
The APRM's cover the Refut, and Startup/ Hot Standby modes with the APRM 15% scram, and the power range with the flow-biased rod block and scram.
The IRM's provide additional protection in the Refuel and Startup/ Hot Standby modes. Thus, the IRM and APRM 15% scram are required in the Refuel and Startup/ Hot Standby modes.
In the power range, the APRM system provides the required protection (Reference FSAR Section 7.5.7).
Thus, the IRM system is not required in the Run mode.
The high reactor pressure, high drywell pressure, reactor low water level, and scram discharge volume high level scrams are required for Startup/ Hot Standby and Run modes of plant operation.
They are, therefore, required to be operational for these modes of reactor operation.
The requirement to have the scram functions, as indicated in Table 3.1.1, operable in the Refuel mode is to assure shifting to the Refuel mode j
during reactor power operation does not diminish the capability of the reactor protection system.
Below 176 psig (analytical limit) turbine first-stage pressure (45% of rated core thermal power for the most limiting balance-of-plant configuration), the scram signals due to turbine stop valve closure or fast closure of turbine control valves are bypassed because flux and pressure scram are adequate to protect the reactor.
If the scram signal due to turbine stop valve closure or fast closure of turbine control valves is bypassed at lower powers, less conservative MCPR and MAPLHGR operating limits may be applied as specified in the CORE OPERATING LIMITS REPORT.
Average Power Range Monitor (APRM)
APRM's #1 and #3 operate contacts in one subchannel and APRM's #2 and #3 operate contacts in the other subchannel. APRM's #4, #5, and #6 are arranged similarly in the other protection trip system.
Each protection trip system has one more APRM than is necessary to meet the minimum number required per channel. This allows the bypassing of one APRM per protection trip system for maintenance, testing, or calibration.
Additional IRM channels have also been provided to allow for bypassing of one such channel.
Amendment No. 79, LAB,152 35
3.1 BASES (Cont'd) remains well above the' safety limit MCPR in all cases, and system pressure does not reach the safety valve settings. The scram setting is approximately 15 inches below the normal operating range and is thus sufficient to avoid spurious scrams.
Turbine Stoo Valve Closure The turbine stop valve closure scram anticipates'the pressure, neutron flux, and heat flux increase that could result from rapid closure of the turbine stop valves.
With a scram trip setting of i 10 percent of valve closure from full open, the resultant increase in surface heat flux is limited such that MCPR remains above the safety limit MCPR even during the worst case transient that assumes the turbine bypass is closed.
Turbine Control Valve Fast Closure The turbine control valve fast closure scram anticipates the pressure, neutron flux, and heat flux increase that could result from fast closure of the turbine control valves due to load rejection exceeding the
{
capability of the bypass valves.
The reactor protection system. initiates a scram when fast closure of the control valves is initiated by the acceleration relay. This setting and the fact that control valve closure time is approximately twice as long as that for the stop valves means that resulting-transients, while similar, are less severe than for stop l
valve closure. MCPR remains above the safety limit MCPR.
Main Steam Line Isolation Valve Closure The low pressure isolation of the main steam lines at 880 psig (as specified in Table 3.2. A) was provided to protect against rapid reactor depressurization and the resulting rapid cooldown of the vessel.
Advantage is taken of the scram feature that occurs when the main steam line isolation valves are closed, to provide for reactor shutdown so that high power operation at low reactor pressure does not occur, thus providing protection for the fuel cladding integrity safety limit.
Operation of the reactor at pressures lower than 785 psig requires the reactor mode switch be in the startup position where protection of the fuel cladding integrity safety limit is provided by the IRM high neutron flux scram and APRM 15% scram.
Thus, the combination of main steam line i
low pressure isolation and isolation valve closure scram assures the availability of neutron flux scram protection over the entire Amendment No. 6, 79, 99,133, M/,152 38