ML20134C687
| ML20134C687 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/28/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20134C691 | List: |
| References | |
| NPF-39-A-119, NPR-85-A-082 NUDOCS 9702040002 | |
| Download: ML20134C687 (22) | |
Text
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- 4 UNITED STATES j
NUCLEAR RESULATORY COMMISSION 2
WASHINGTON, D.C. 20SE0001 49.....,o PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated May 20, 1996, 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 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.
9702040002 970128 PDR ADOCK 05000352 p
j 1
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-39 is hereby amended to read as fol.'ows:
Technical Soecifications i
l The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, as revised through Amendment No.119, 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 date of issuance, and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION s
John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 28, 1997 l
i l
J
ATTACHMENT TO LICEWSE AMENDMENT NO. 110 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 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 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 i
3/4 9-17 3/4 9-17 1
3/4 9-18 3/4 9-18 4
B 3/4 4-6 B 3/4 4-6 B 3/4 4-6a B 3/4 9-2 B 3/4 9-2 B 3/4 9-2a i
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3/4.4.9 RESIDUAL MEAT REMOVAL HOT SHUTDOWN 2
LIMITING CONDITION FOR OPERATION 3.4.9.1 Two (2) independent RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** ***
Each independent RHR shutdown cooling subsystem shall consist of at least:
a.
One OPERABLE RHR heat exchanger, not common to the two (2) independent subsystems.
APPLICABILITY:
OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.
ACTION:
a.
With im than the above required independent kHR shutdown cooling subsystems OPERABLE, immediately initiate corrective action to return the required independent subsystems to OPERABLE status as soon as possible.
Within I hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the availability of at least one alternate method capable of decay heat removal for each inoperable independent RHR shutdown cooling subsystem.
Be in at least COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.****
b.
With no independent RHR shutdown cooling subsystem in operation, immediately initiate corrective action to return at least one (1) independent subsystem to operation as soon as possible. Within I hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.
SURVEILLANCE REQUIREMENTS 4.4.9.1 At least one independent RHR shutdown cooling subsystem or alternate method l
shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 0ne independent RHR shutdown cooling subsystem may be inoperable 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 surveillance testing provided the other independent subsystem is OPERABLE and in operation.
- The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period provided the other independent subsystem is OPERABLE.
l
- The independent RHR shutdown cooling subsystem may be removed from operation during l
hydrostatic testing.
- Whenever two or more RHR 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.
LIMERICK - UNIT 1 3/4 4-25 Amendment No. 97,119
REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** ***
APPLICABILITY: OPERATIONAL CONDITION 4.
ACTION: #
a.
With one (1) or two (2) RHR shutdown cooling subsystems inoperable:
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an alternate method of decay heat removal is available for each 4
inoperable RHR shutdown cooling subsystem.
i b.
With no RHR shutdown cooling subsystems in operation and no recirculation pump in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulating by an alternate method; and 2.
Once per hour monitor reactor coolant temperature and pressure.
SURVEILLANCE RE0VIREMENTS 4.4.9.2 At least one (1) RHR shutdown cooling subsystem or recirculation pump is operating or an alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up two (2) hours per eight (8) hour period.
One (1) RHR shutdown cooling subsystem may be inoperable for up to two (2) hours for the performance of Surveillances.
The shutdown cooling subsystem may be removed from operation during hydrostatic testing.
Separate Action entry is allowed for each shutdown cooling subsystem.
LIMERICK - UNIT 1 3/4 4-26 Amendment No. 97, 119
REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION k
HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 One (1) RHR shutdown cooling subsystem shall be OPERABLE and in operation.
- APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 22 feet above the top of the reactor pressure vessel flange.
ACTION:
With the required RHR shutdown cooling subsystem inoperable:
a.
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an alternate method of decay heat removal is available.
b.
With the required action and associated completion time of Action "a" above not met.
1.
Immediately suspend loading of irradiated fuel assemblies into the reactor pressure vessel; and 2.
Immediately initiate action to restore REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY to OPERABLE status; and 3.
Immediately initiate action to restore one (1) Standby Gas Treatment subsystem to OPERABLE status; and 4.
Immediately initiate action to restore isolation capability in each required Refueling Floor secondary containment penetration flow path not isolated.
c.
With no RHR shutdcwn cooling subsystem in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulation by an alternate method; and 2.
Once per hour monitor reactor coolant temperature.
SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one (1) RHR shutdown cooling subsystem, or an alternate method, shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The required RHR shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.
LIMERICK - UNIT 1 3/4 9-17 Amendment No. 97,119
REFUELING OPERATIONS i
LOW WATER LEVEL LIMITING CONDITION FOR OPERATION i
3.9.11.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and one (1)
RHR shutdown cooling subsystem shall be in operation.
- s APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor i
vessel and the water level is less than 22 feet above the top of l
the reactor pressure vessel flange.
ACTION:
l) a.
With one (1) or two (2) required RHR shutdown cooling subsystems 1
inoperable:
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.
i b.
With the requi. red action and associated completion time of Action "a" above not met:
)
i 1.
Immediately initiate action to restore REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY to OPERABLE status; and i
2.
Immediately initiate action to restore one (1) Standby Gas j
Treatment subsystem to OPERABLE status; and d
3.
Immediately initiate action to restore isolation capability in each I
required Refueling Floor secondary containment penetration flow path not isolated.
1
{
c.
With no RHR shutdown cooling subsystem in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulation by an alternate method; and 2.
Once per hour monitor reactor coolant temperature.
SURVEILLANCE REQUIREMENTS j
l 4.9.11.2 At least one (1) RHR shutdown cooling subsystem, or an alternate method, shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4 l
i The required operating shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.
i 4
LIMERICK - UNIT 1 3/4 9-18 Amendment No. 97,119
REACTORCOOLANTSYSTEM BASES 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES Double isolation valves are provided on each of the main steam lines to minimize the potential leakage paths from the containment in case of a line break.
Only one valve in each line is required to maintain the integrity of the containment, however, single failure considerations require that two valves be OPERABLE. The surveillance requirements are based on the operating history of this type valve.
The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks.
The minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges.
3/4.4.8 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.
Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.
The inservice inspection program for ASME Code Class 1, 2, and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). Additionally, the Inservice Inspection Program conforms to the NRC staff positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," as approved in NRC Safety Evaluations dated March 6, 1990 and October 22, 1990.
3/4.4.9 RESIDUAL HEAT REMOVAL The RHR system is required to remove decay heat and sensible heat in order to maintain the temperature of the reactor coolant.
RHR shutdown cooling is comprised of four (4) subsystems which make two (2) loops.
Each loop consists of two (2) motor driven pumps, a heat exchanger, and associated piping and valves.
Both loops have a common suction from the same recirculation loop.
Two (2) redundant, manually controlled shutdown cooling subsystems of the RHR System can provide the required decay heat removal capability.
Each pump discharges the reactor coolant, after it has been cooled by circulation through the respective heat exchangers, to the reactor via the associated recirculation loop or to the reactor via the low pressure coolant injection pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The RHR shutdown cooling mode is manually controlled.
An OPERABLE RHR shutdown cooling subsystem consists of an RHR pump, a heat exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path.
In HOT SHUTDOWN condition, the requirement to maintain OPERABLE two (2) independent RHR shutdown cooling subsystems means that each subsystem considered OPERABLE must be associated with a different heat exhanger loop, i.e., the "A" RHR heat exchanger with the "A" RHR pump or the "C" RHR pump, and the "B" RHR heat exchanger with the "B" RHR pump or the "D" RHR pump are two (2) independent RHR shutdown cooling subsystems. Only one (1) of the the two (2) RHR pumps associated with each RHR heat exchanger loop is LIMERICK - UNIT 1 B 3/4 4-6 Amendment No. 497-977 119
3/4.4.9 RESIDUAL HEAT REMOVAL (Cont'd) required to be OPERABLE for that independent subsystem to be OPERABLE.
During COLD SHUTOOWN and REFUELING conditions, however, the subsystems not only have a common 4
suction source, but are allowed to have a common heat exchanger and common discharge piping. To meet the LC0 of two (2) OPERABLE subsystems, both pumps in one (1) loop or one (1) pump in each of the two (2) loops must be OPERABLE. Since the piping and heat exchangers are passive components, that are assumed not to fail, they are allowed to be common to both subsystems. Additionally, each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown cooling mode for removal of decay heat. Operation (either continuous or intermittent) il of one (1) subsystem can maintain and reduce the reactor coolant temperature as required. However, to ensure adequate core flow to allow for accurate average reactor coolant temperature monitoring, nearly continuous operation is required.
Alternate decay heat removal methods are available to operators. These alternate methods of decay heat removal can be verified available either by calculation (which includes a review of component and system availability to verify that an alternate decay heat removal method is available) or by demonstration, and that a method of coolant mixing be operational. Decay heat removal capability by ambient losses can be i
considered in evaluating alternate decay heat removal capability.
4 I
LIMERICK - UNIT I B 3/4 4-6a Amendment No. 119 1
REFUELING OPERATIONS BASES 3.4.9.6 REFUE. LING PLATFORM The OPERABILITY requirements ensure that (1) the refueling platform will be used for handling control rods and fuel assemblies within the reactor pressure vessel, (2) each hoist has sufficient load capacity for handling fuel assemblies and control rods, (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations, and (4) inadvertent criticality will not occur due to fuel being loaded into a unrodded cell.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL The restriction on movement of loads in excess of the nominal weight of a fuel assembly and associated lifting device over other fuel assemblies in the storage pool ensures that in the event this load is dropped 1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical erray. This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P0OL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
This minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.10 CONTROL R00 REMOVA1 These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality.
The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.
3/4.9.11 RESIDUAL HEAT RFMOVAL AND COOLANT CIRCULATION Irradiated fuel in the shutdown reactor core generates heat during the decay of fission products and increases the temperature of the reactor coolant. This decay heat must be removed by the RHR system to maintain adequate reactor coolant temperature.
RHR shutdown cooling is comprised of four (4) subsystems which make two (2) loops.
Each loop consists of two (2) motor driven pumps, a heat exchanger, and associated piping and valves.
Both loops have a common suction from the same recirculation loop. Two (2) redundant, manually controlled shutdown cooling subsystems of the RHR system provide decay heat removal.
Each pump discharges the reactor coolant, after circulation through the' respective heat exchanger, to the reactor via the associated recirculation loop.
The RHR heat exchangers transfer heat to the RHR Service Water System.
An OPERABLE RHR shutdown cooling subsystem consists of one (1) OPERABLE RHR pump, one (1) heat exchanger, and the associated piping and valves.
The requirement for LIMERICK - UNIT 1 B 3/4 9-2 Amendment No. 88 -97, 119 7
3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT C RCULATION (Cont'd) having one (1) RHR shutdown cooling subsystem OPERABLE ensures that 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F, and 2) sufficient coolant circulation would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the poison in the event it becomes necessary to actuate the standby liquid control system.
The requirement to have two (2) RHR shutdown cooling subsystems OPERABLE when there is less than 22 feet of water above the reactor vessel flange ensures that a single failure of the operating loop will not result in a complete loss of residual heat removal capability.
With the reactor vessel head removed and 22 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR subsystem, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
To meet the LC0 of the two (2) subsystems OPERABLE when there is less than 22 feet of water above the reactor vessel flange, both pumps in one (1) loop or one (1) pump in each of the two (2) loops must be OPERABLE.
The two (2) subsystems have a common suction source and are allowed to have a common heat exchanger and common discharge piping. Additionally, each shutdown cooling subsystem can provide the required decay heat removal capability; however, ensuring operability of the other shutdown cooling subsystem provides redundancy.
The required cooling capacity of an alternate method of decay heat removal should be ensured by verifying its capability to maintain or reduce reactor coolant temperature either by calculation (wnich includes a review of component and system availability to verify that an alternate decay heat removal method is available) or by demonstration.
Decay heat removal capability by ambient losses can be considered in evaluating alternate decay heat removal capability.
With the required decay heat removal subsystem (s) inoperable and the required alternate method (s) of decay heat removal not available in accordance with Action "a",
additional actions are required to minimize any potential fission product release to the environment. This includes ensuring Refueling Floor Secondary Containment is OPERABLE; one (1) Standby Gas Treatment subsystem is OPERABLE; and Secondary Cor.tainment isolation capability (i.e., one (1) Secondary Containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration not isolated that is assumed to be isolated to mitigate radioactive releases.
This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.
It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.
If, however, any required component is inoperable, then it must be restored to OPERABLE status.
In this case, the surveillance may need to be performed to restore the component to OPERABLE status. Actions must continue until all required components are OPERABLE.
If no RHR subsystem is in operation, an alternate method of coolant circulation is required to be established within one (1) hour.
The Completion Time is modified such that one (1) hour is applicable separately for each occurrence involving a loss of coolant circulation.
LIMERICK - UNIT 1 B 3/4 9-2a Amendment No. 119
^ ' - ~
4 UNITED STATES f
NUCLEAR RE2ULATORY COMMISSION If WASHINGTON, D.C. 206d50001
\\,...../
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPEPf d o LICENSE Amendment No. 82 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated May 20, 1996, 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 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.
-=
l
^
' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 4
J and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby l
amended to read as follows:
Technical Specifications l
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
82, are hereby incorporated in the 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 date of issuance, and j
shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 1
P' i
John F. Stolz, irec or Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the Technical Specifications l
l Date of Issuance:
January 28, 1997 f
i a
1 i
4 i
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 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.
Remoye Instr _t 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-18 8 3/4 4-6 B 3/4 4-6 B 3/4 4-6a B 3/4 9-2 8 3/4 9-2 B 3/4 9-2a
REACT 0R COOLANT SYSTEM 3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.1 Two (2) independent RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling
. subsystem shall be in operation. * ** ***
Each independent RHR shutdown cooling subsystem shall consist of at least:
a.
One OPERABLE RHR heat exchanger, not common to the two (2) independent subsystems.
APPLICABILITY:
OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.
ACTION:
With less than the above required independent RHR shutdown cooling subsystems a.
1 OPERABLE, immediately initiate corrective action to return the required independent subsystems to OPERABLE status _as soon as possible.
Within I hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the availability of at least one alternate method capable of decay heat removal for each inoperable independent RHR shutdown cooling subsystem.
Be in at least COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.****
b.
With no independent RHR shutdown cooling subsystem in operation, immediately initiate corrective action to return at least one (1) independent subsystem to operation as soon as possible. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.
SURVEILLANCE REQUIREMENTS 4.4.9.1 At least one independent RHR shutdown cooling subsystem or alternate method I
shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 0ne independent RHR shutdown cooling subsystem may be inoperable 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 surveillance testing provided the other independent subsystem is OPERABLE and in operation.
- The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period provided the other independent subsystem is OPERABLE.
l
- The independent RHR shutdown cooling subsystem may be removed from operation during l
hydrostatic testing.
- Whenever two or more RHR 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.
LIMERICK - UNIT 2 3/4 4-25 Amendment No. 64, 82
l
COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** ***
APPLICABILITY: OPERATIONAL CONDITION 4.
j ACTION: #
a.
With one (1) or two (2) RHR shutdown cooling subsystems inoperable:
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an i
alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem, b.
With no RHR shutdown cooling subsystems in operation and no recirculation pump in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulating by an alternate method; and 2.
Once per hour monitor reactor coolant temperature and pressure.
SURVEILLANCE RE0VIREMENTS 4.4.9.2 At least one (1) RHR shutdown cooling subsystem or recirculation pump is operating or an alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up two (2) hours per eight hour (8) period.
One (1) RHR shutdown cooling subsystem may be inoperable for up to two (2) hours for the performance of Surveillances.
The shutdown cooling subsystem may be removed from operation during hydrostatic testing.
Separate Action entry is allowed for each shutdown cooling subsystem.
LIMERICK - UNIT 2 3/4 4-26 Amendment No. 64, 82
, REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 One (1) RHR shutdown cooling subsystem shall be OPERABLE and in operation.
- l APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 22 feet above the top i
of the reactor pressure vessel flange.
ACTION:
a.
With the required RHR shutdown cooling subsystem inoperable:
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an alternate method of decay heat removal is available.
b.
With the required action and associated completion time of Action "a" above not met.
1.
Immediately suspend loading of irradiated fuel assemblies into the reactor pressure vessel; and 2.
Immediately initiate action to restore REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY to OPERABLE status; and 3.
Immediately initiate action to restore one (1) Standby Gas Treatment subsystem to OPERABLE status; and 4.
Immediately initiate action to restore isolation capability in each required Refueling Floor secondary containment penetration flow path not isolated, c.
With no RHR shutdown cooling subsystem in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulation by an alternate method; and 2.
Once per hour monitor reactor coolant temperature.
SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one (1) RHR shutdown cooling subsystem, or an alternate method, shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The required RHR shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.
LIMERICK - UNIT 2 3/4 9-17 Amendment No. 64, 82
AEFUELING OPERATIONS l
LOW WATER LEVEL j
LIMITING CONDITION FOR OPERATION l
3.9.11.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and one (1)
RHR shutdown cooling subsystem shall be in operation.
- APPLICABILITh OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 22 feet above the top of the reactor pressure vessel flange.
ACTION:
a.
With one (1) or two (2) required RHR shutdown cooling subsystems inoperable:
1.
Within one (1) hour, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.
b.
With the required action and associated completion time of Action "a" above not met:
1.
Immediately initiate action to restore REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY to OPERABLE status; and 2.
Immediately initiate action to restore one (1) Standby Gas Treatment subsystem to OPERABLE status; and 3.
Immediately initiate action to restore isolation capability in each required Refueling Floor secondary containment penetration flow path not isolated.
c.
With no RHR shutdown cooling subsystem in operation:
1.
Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify reactor coolant circulation by an alternate method; and 2.
Once per hour monitor reactor coolant temperature.
SURVEILLANCE RE0VIREMENTS 4.9.11.2 At least one (1) RHR shutdown cooling subsystem, or an alternate method, shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The required operating shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.
LIMERICK - UNIT 2 3/4 9-18 Amendment No. 64, 82
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BASES 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES Double isolation valves are provided on each of the main steam lines to i
minimize the potential leakage paths from the containment in case of a line break.
Only one valve in each line is required to maintain the integrity of the 4
containment, however, single failure considerations require that two valves be OPERABLE. The surveillance requirements are based on the operating history of i
this type valve.
The maximum closure time has been selected to contain fission I
products and to ensure the core is not uncovered following line breaks. The j
minimum closure time is consistent with the assumptions in the safety analyses to j
prevent pressure surges.
i 3/4.4.8 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable 3
l level throughout the life of the plant.
l Components of the reactor coolant system were designed to provide access to l
permit inservice inspections in accordance with Section XI of the ASME Boiler and i
Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.
The inservice inspection program for ASME Code Class 1, 2, and 3 components y
will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except where i
specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i).
Additionally, the Inservice Inspection Program conforms to the i
NRC staff positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC j
in BWR Austenitic Stainless Steel Piping," as approved in NRC Safety Evaluations dated March 6, 1990 and October 22, 1990, t
i 3/4.4.9 RESIDUAL HEAT REMOVAL i
The RHR system is required to remove decay heat and sensible heat in order to maintain the temperature of the reactor coolant.
RHR shutdown cooling is comprised of four (4) subsystems which make two (2) loops.
Each loop consists of two (2) motor i
driven pumps, a heat exchanger, and associated piping and valves.
Both loops have a
{
common suction from the same recirculation loop. Two (2) redundant, manually controlled shutdown cooling subsystems of the RHR System can provide the required decay heat removal capability.
Each pump discharges the reactor coolant, after it has been I
cooled by circulation through the respective heat exchangers, to the reactor via the 1
associated recirculation loop or to the reactor via the low pressure coolant injection
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pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The
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RHR shutdown cooling mode is manually controlled.
J j
An OPERABLE RHR shutdown cooling subsystem consists of an RHR pump, a heat i
exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path.
In HOT SHUTDOWN condition, the requirement to maintain OPERABLE two (2) independent RHR i
shutdown cooling subsystems means that each subsystem considered OPERABLE must be associated with a different heat exhanger loop, i.e., the "A" RHR heat exchanger with j
the "A" RHR pump or the "C" RHR pump, and the "B" RHR heat exchanger with the "B" RHR pump or the "D" RHR pump are two (2) independent RHR shutdown cooling subsystems. Only a
j one (1) of the two (2) RHR pumps associated with each RHR heat exchanger loop is LIMERICK - UNIT 2 8 3/4 4-6 Amendment No. 42 -64, 82 7
i l
i
]
- 1/4.4.9 RESIDUAL HEAT REMOVAL (Cont'd) j required to be OPERABLE for that independent subsystem to be OPERABLE.
During COLD i
SHUTDOWN and REFUELING conditions, however, the subsystems not only have a common i
suction source, but are allowed to have a common heat exchanger and common discharge l
piping. To meet the LC0 of two (2) OPERABLE subsystems, both pumps in one (1) loop or one (1) pump in each of the two (2) loops must be OPERABLE.
Since the piping and heat exchangers are passive components, that are assumed not to fail, they are allowed to be common to both subsystems. Additionally, each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown 4
cooling mode for removal of decay heat. Operation (either continuous or intermittent) 1 of one (1) subsystem can maintain and reduce the reactor coolant temperature as j
required. However, to ensure adequate core flow to allow for accurate average reactor coolant temperature monitoring, nearly continuous operation is required.
Alternate decay heat removal methods are available te operators. These alternate methods of decay heat removal can be verified available either by calculation (which includes a review of component and system availability to verify that an alternate t
decay heat removal method is available) or by demonst"ation, and that a method of j
coolant mixing be operational. Decay heat removal capability by ambient losses can be considered in evaluating alternate decay heat removal capability.
1i i
i i
i LIMERICK - UNIT 2 B 3/4 4-6a Amendment No. 82
4EFUELING OPERATIONS BASES 3.4.9.6 REFUELING PLATFORM The OPERABILITY requirements ensure that (1) the refueling platform will be used for handling control rods and fuel assemblies within the reactor pressure vessel, (2) each hoist has sufficient load capacity for handling fuel assemblies and control rods, (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations, and (4) inadvertent criticality will not occur due to fuel being loaded into a unrodded cell.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L The restriction on movement of loads in excess of the nominal weight of a fuel assembly and associated lifting device over other fuel assemblies in the storage pool ensures that in the event this load is dropped 1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P0OL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. This minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.10 CONTROL R0D REMOVAL These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality.
The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully l
withdrawn.
3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION Irradiated fuel in the shutdown reactor core generates heat during the decay of fission products and increases the temperature of the reactor coolant.
This decay heat must be removed by the RHR system to maintain adequate reactor coolant temperature.
1 RHR shutdown cooling is comprised of four (4) subsystems which make two (2) loops.
Each loop consists of two (2) motor driven pumps, a heat exchanger, and associated piping and valves.
Both loops have a common suction from the same j
recirculation loop.
Two (2) redundant, manually controlled shutdown cooling subsystems j
of the RHR system provide decay heat removal.
Each pump discharges the reactor coolant, after circulation through the respective heat exchanger, to the reactor via the associated recirculation loop.
The RHR heat exchangers transfer heat to the RHR Service Water System.
An OPERABLE RHR shutdown cooling subsystem consists of one (1) OPERABLE RHR pump, one (1) heat exchanger, and the associated piping and valves.
The requirement for LIMERICK - UNIT 2 B 3/4 9-2 Amendment No. 59;-64, 82
)
i i
- = - -.
. - - --., -..~
4 14.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION (Cont'd) l i
having one (1) RHR shutdown cooling subsystem OPERABLE ensures that 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F, and 2) sufficient coolant circulation would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the poison in the event it becomes necessary to l
actuate the standby liquid control system.
The requirement to have two (2) RHR shutdown cooling subsystems OPERABLE when there is less than 22 feet of water above the reactor vessel flange enrures that a single failure of the operating loop will not result in a complete loss of residual 4
heat removal capability. With the reactor vessel head removed and 22 feet of water above the reactor vessel flange, a large heat sink is available for i
core cooling. Thus, in the event of a failure of the operating RHR subsystem, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
l To meet the LCO of the two (2) subsystems OPERABLE when there is less than 22 i
feet of water above the reactor vessel flange, both pumps in one (1) loop or one (1) pump in each of the two (2) loops must be OPERABLE.
The two (2) subsystems have a j
common suction source and are allowed to have a common heat exchanger and common discharge piping. Additionally, each shutdown cooling subsystem can provide the required decay heat removal capability; however, ensuring operability of the other shutdown cooling subsystem provides redundancy.
The required cooling capacity of an alternate method of decay heat removal should be ensured by verifying its capability to maintain or reduce reactor coolant temperature either by calculation (which includes a review of component and system availability to verify that an alternate decay heat removal method is available) or by demonstration.
Decay heat removal capability by ambient losses can be considered in 4
j evaluating alternate decay heat removal capability.
With the required decay heat removal subsystem (s) inoperable and the required I
alternate method (s) of decay heat removal not available in accordance with Action "a",
j additional actions are required to minimize any potential fission product release to the environment. This includes ensuring Refueling Floor Secondary Containment is OPERABLE; one (1) Standby Gas Treatment subsystem is OPERABLE; and Secondary i
Containment isolation capability (i.e., one (1) Secondary Containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration not isolated that is
}
assumed to be isolated to mitigate radioactive releases.
This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.
It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.
If, however, any required component is inoperable, then it must be restored to OPERABLE i
status.
In this case, tb. :urveillance may need to be performed to restore the component to OPERABLE status. Actions must continue until all required components are OPERABLE.
If no RHR subsystem is in operation, an alternate method of coolant circulation is required to be established within one (1) hour. The Completion Time is modified such i
that one (1) hour is applicable separately for each occurrence involving a loss of coolant circulation.
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LIMERICK - UNIT 2 B 3/4 9-2a Amendment No. 82
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