ML20095A027
| ML20095A027 | |
| Person / Time | |
|---|---|
| Site: | Limerick |
| Issue date: | 11/30/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20095A029 | List: |
| References | |
| NPF-85-A-070 NUDOCS 9512060282 | |
| Download: ML20095A027 (9) | |
Text
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9pmeu UNITED STATES p-j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2066dW1001
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-85 1.
The Nuclear Regulatory Comission (the Comission) has found that:
3.
The application for amendment by Philadelphia Electric Company (the licensee) dated June 23, 1995, 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 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 endangering the health and e
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.
l 9512060282 951130 DR ADOCK 0500 3
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\\ 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 1
and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows.
1 Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 70
, are hereby incorporated into this license.
Philadelphia Electric 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 dete of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 4
John F. Stolz, Director i
Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date: November 30, 1995
s ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached page. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
i Remove Insert 3/4 5-1 3/4 5-1 3/4 5-2 3/4 5-2 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 3/4 7-1 3/4 7-1 3/4 7-3 3/4 7-3 e
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3/d.5EMERGENCYCOREC0QLINGSYSTEMS 3/4.5.1 ECCS - OPERATING LIMITING QNDITIONFOROPERATION 3.5.1 The emergency core cooling systems shall be OPERABLE with:
a.
The core spray system (CSS) consisting of two subsystems with each subsystem comprised of:
1.
Two OPERABLE CSS pumps, and 2.
An OPERABLE flow patch capable of taking suction from the suppression chamber and transferring the water through the spray sparger to the reactor vessel.
b.
The low pressure coolant injection (LPCI) system of the residual heat removal system consisting of four subsystems with each subsystem comprised of:
1.
One OPERABLE LPCI pump, and 2.
An OPERABLE flow rath capable of taking suction from the suppression chamber and transferring the water to the reactor vessel.
c.
The high pressure coolant injection (HPCI) system consisting of:
1 1.
One OPERABLE HPCI pump, and 2.
An OPERABLE flow path capable of taking suction from the 4
suppression chamber and transferring the water to the reactor
- vessel, d.
The automatic depressurization system (ADS) with at least five j
APPLICABILITY:
OPERATIONAL CONDITION 1, 2* ** #, and 3* ** ## ###.
- The HPCI system is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 200 psig.
- See Special ' Test Exception 3.10.6.
- Two LPCI subsystems of the RHR system may be inoperable in that they are aligned in the shutdown cooling.wde when reactor vessel pressure is less than the RHR Shutdown cooling permissive setpoint.
- During the 14 day extended A0T period allowed for installation of the common ESW and RHRSW system Modifications P-0166, P-0167, and P-0168 during the Unit I sixth refueling outage (IR06), in addition to the inoperable 'A' and 'C' LPCI subsystems of the RHR system and the.'A' CSS subsystem, the 'B' LPCI subsystem of the RHR system may be inoperable in that it is aligned in the shutdown cooling mode when reactor vessel pressure is less than the RHR Shutdown Cooling permissive setpoint.
4 LIMERICK - UNIT 2 3/4 5-1 Amendment No. 70
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EMERGENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
a.
For the core spray system:
1.
With.one CSS subsystem inoperable, provided that at least two LPCI i
subsystems are OPERABLE, restore the inoperable CSS subsystem to i
OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.#
4 2.
With both CSS subsystems inoperable, be in at least HOT SHUTDOWN
}
within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i b.
For the LPCI system:
i 1.
With one LPCI subsystem inoperable, provided that at least ora CSS l-subsystem is OPERABLE, restore the inoperable LPCI pump to OPEPABLE status within 30 days or be in at least HOT SHUTDOWN within the l
next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I 2.
With one RHR cross-tie valve (HV-51-282 A or B) open, or power not removed from one closed RHR cross-tie valve operator, close the open valve and/or remove power from the closed valves operator within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I 3.
With no RHR cross-tie valves (HV-51-282 A, 8) closed, or power l
not removed from both closed RHR cross-tie valve operators, or with one RHR cross-tie valve open and power not removed from j
the other RHR cross-tie valve operator, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
With two LPCI subsystems inoperable, provided that at least one CSS subsystem is OPERABLE, restore at least three LPCI subsystems to l
OPERABLE status within 7 days or be in at least HOT SHUTDOWN within i
the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.#.l '
5.
With three LPCI subsystems inoperable, provided that both CSS subsystems are OPERABLE, restore at least two LPCI subsystems to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 6.
With all four LPCI subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
l d
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- Whenever both shutdown cooling subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature j
as low as practical by use of alternate heat removal methods.
1 i
- The Allowed Outage Times (A0Ts) of the 'A' Core Spray subsystem and the 'A' and 'C' l
LPCI subsystems may be extended up to 14 days to allow for installation of the common l
ESW and RHRSW system Modifications P-0166, P-0167, and P-0168 during the Unit I sixth refueling outage (IR06).
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. LIMERICK - UNIT 2 3/4 5 Amendment No. 58, 70 l
_.. - = _ -., - -. -
CONTAINMENT SYSTEMS
{
SUPPRESSION POOL SPRAY LIMITING CONDITION FOR OPERATION
}
t 3.6.2.2 The suppression pool spray mode of the residual heat removal (RHR)-
j system shall be OPERABLE with two independent loops, each loop consisting of:
a.
b.
An OPERABLE flow path capable of recirculating water from the l
suppression chamber through an RHR heat exchanger and the
(
suppression pool spray sparger(s).
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APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
1 ACTION:
t a.
With one suppression pool spray loop inoperable, restore the inoperable loop to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following l
. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.#
(
b.
With both suppression pool spray loops inoperable, restore at least j
one loop to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
- within the il following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SUtVEILLANCE tEOUIREMENTS I
4.5.2.2 T1e suppression pool spray mode of the RHR system shall be demonstrated OPERABLE:
l I
l a.
At least once per 31 days by verifying that each valve (manual, power-l operated, or automatic) in the flow path that is not locked, sealed, i
or otherwise secured in position, is in its correct position.
b.
By verifying that each of the required RHR pumps develops a flow of at least 500 gpm on recirculation flow through the RHR heat exchanger i
and the suppression pool spray sparger when tested pursuant to Speci-fication 4.0.5.
1 i
1
- Whenever both RHR subsystems are inoperable, if unable to attain C0'l i
SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
i-
- The allowed outage time (A0T) of the 'A' loop of the suppression pool spray i
mode of the RHR system ray be extended up to 14 days to allow for installation I
of the common ESW and RHRSW system Modifications P-0166, P-0167 and P-0168 during the Unit I sixth refueling outage (IR06).
i LIMERICK - UNIT 2 3/4 6-15 Amendment No. M, 70 4
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CONTAINMENT SYSTEMS SUPPRESSION POOL COOLING LIMITING CONDITION FOR OPERATION 3.6.2.3 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent loops, each loop consisting of:
i a.
An OPERABLE flow path capable of recirculating water from the suppression chamber through an RHR heat exchanger.
\\
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With one suppression pool cooling loop inoperable, restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.#
b.
With both suppression pool cooling loops inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
- within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.6.2.3 The suppression pool cooling mode of the RHR system shall be demonstrated OPERABLE:
i a.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
By verifying that each of the required RHR pumps develops a flow of at least 10,000 gpm on ret.irculation flow through the flow path including.
the RHR heat exchanger and its associated closed bypass valve, the 4
suppression pool and the full flow test line when tested pursuant to Specification 4.0.5.
j
- Whenever both RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as l
practical by use of alternate heat removal methods.
- The Allowed Outage Time (A0T) of the 'A' loop of the suppression pool cooling mode of the RHR system may be extended up to 14 days to allow for installation of the common ESW and RHRSW system Modifications P-0166, P-0167 and P-0168 during the Unit 1 sixth refueling outage (1R06).
LIMERICK - UNIT 2 3/4 6-16 Amendment No. 30, 70
3/4.7 PLANT SYSTEMS 3/4.7.I SERVICE WATER SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM - COMMON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.1 At least the following independent residual heat removal service water (RHRSW) system subsystems, with each subsystem comprised of:
a.
Two OPERABLE RHRSW pumps, and b.
An OPERABLE flow path capable of taking suction from the RHR service water pumps wet pits which are supplied'from the spray pond or the cooling tower basin and transferring the water through one Unit 2 RHR heat exchanger, shall be OPERABLE:
a.
In OPERATIONAL CONDITIONS 1, 2, and 3, two subsystems.
1 b.
In OPERATIONAL CONDITIONS 4 and 5, the subsystem (s) associated with systems and components required OPERABLE by Specification 3.4.9.2, 3.9.11.1, and 3.9.11.2.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2, or 3:
1.
With one RMRSW pump inoperable, restorc the inoperable pump to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With one RHRSW pump in each subsystem inoperable, restore at least one of the inoperable RHRSW pumps to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With one RHRSW subsystem otherwise inoperable, restore the inoperable subsystem to OPERABLE status with at least one OPERACLE RHRSW pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.#
4.
With both RHRSW subsystems otherwise inoperable, restore at least one subsystem to OPERABLE statas within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
- within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Whenever both RHRSW subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
- The Allowed Outage time (A0T) of the 'A' RHRSW subsystem may be extended up to 14 days to allow for installation of the common ESW and RHRSW system Modifications P-0166, P-0167 and P-0168 during the Unit 1 sixth refueling outage (1R06).
LIMERICK - UNIT 2 3/4 7-1 Amer 3nent No. 30, 70
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM - C0 2 0N SYSTEM LIMITING CONDITION FOR OPERATION i
3.7.1.2. At least the following independent emergency service water system loops, with each loop comprised of:
h
- a. Two OPERABLE emergency service water pumps, and
- b. An OPERABLE flow path capable of taking suction from the emergency service water pumps wet pits which are supplied from the spray pond or l
the cooling tower basin and transferring the water to the associated Unit 2 and common safety-related equipment, shall be OPERABLE:
4 i
i i
- a. In OPERATIONAL CONDITIONS 1, 2, and 3, two loops.
- b. In OPERATIONAL CONDITIONS 4, 5, and *, one loop.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, 5, and *.
ACTION:
d
- a. In OPERATION CONDITION 1, 2, or 3:
i-l 1.
With one emergency service water pump inoperable, restore the inoperable pump to OPERABLE status within 45 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With one emergency service water pump in each loop inoperable, restore at least one inoperable pump to OPERABLE status within 30 days or be in at i
least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the l
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With one emergency service water system loop otherwise inoperable, declare,
)
all equipment aligned to the inoperable loop inoperable **f, restore the inoperable loop to OPERABLE status with at least one OPERABLE pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD
[
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- When handling irradiated fuel in the secondary containment.
i i
- The diesel generators may be aligned to the OPERABLE emergency service water system i
loop provided confirmatory flow testing has been performed. Those diesel generators i
not aligned to the OPERABLE emergency service water system loop shall be declared inoperable and the actions of 3.8.1.1 taken.
j i
- The Allowed Outage Time (A0T) of the 'A' loop of the Emergency Service Water system may be extended up to 14 days to allow for installation of the common ESW and RHRSW 2
system Modifications P-0166, P-0167 and P-0168 during the Unit I sixth refueling outage (IR06).
i i
l LIMERICK - UNIT 2 3/4 7-3 Amendment No. 78, 70 i
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