ML20086P946
| ML20086P946 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/18/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20086P948 | List: |
| References | |
| NPF-39-A-097, NPF-85-A-061 NUDOCS 9507270224 | |
| Download: ML20086P946 (18) | |
Text
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,gnrefug UNITED STATES y
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NUCLEAR REGULATORY COMMISSION 5
WASHINGTON, D.C. 20066 0001
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PHILADELPHIA ELECTRIC COMPAN1 I
DOCKET NO. 50-352 LIMERICK GENERATING STATION. UMLL1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the l'
licensee) dated August 31, 1994, as supplemented by letter dated July 3, 1995, complies with the standards and requirements of the-l Atomic Energy Act of 1954, as amended (the Act), and the Commission's l
rules and regulations set forth in 10 CFR Chapter I; l'
B.
The facility will operate in conformity with the application, the l
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 i
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 1
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.
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9507270224 950718 PDR ADDCK 05000352 P
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j 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-39 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.
{
97, are hereby incorporated into this. license.
Philadelphia Electric I
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 i
be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
t
.w d John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment-Changes to the i
Technical Specifications Date of Issuance:
July 18, 1995 5
I i
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a ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 I
i 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 l
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 8 3/4 9-2 B 3/4 9-2
- 3/4.4.9 RESIDUAL HEAT REMOVAL 1
HOT SHUTDOWN i
LIMITING CONDITION FOR OPERATION j
3.4.9.1.
Two* shutdown cooling mode loops of the residual heat removal (RHR) j system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation ** ***
with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.
ACTION:
a.
With less than the above required RHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status 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 /> 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-l l
of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.
Be in.at least COLD i
SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.****
j b.
With no RHR shutdown cooling mode loop in operation, immediately initiate corrective action to return at least one loop to operation t
as soon as possible. Within I hour establish reactor coolant circu-1ation 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 shutdown cooling mode loop of the residual heat removal l
system or 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 />.
- 0ne RHR shutdown cooling mode loop 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 loop 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 loop is OPERABLE.
I
- The RHR shutdown cooling mode loop may be removed from operation during hydrostatic testing.
- Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUT 00WN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
J LIMERICK - UNIT 1 3/4 4-25 Amendment No. 97 I
l
.c.
REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two* shutdown cooling mode loops of the residual heat removal (RHR)-
system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation ** ***
with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY: OPERATIONAL CONDITION 4.
ACTION:
a.
With less than the above required RHR shutdown cooling mode loops OPERABLE, 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 l
of decay heat removal for each inoperable RHR shutdown cooling mode loop.
b.
With no RHR shutdown cooling mode loop in operation, 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 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or 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 />.
- 0ne RHR shutdown cooling mode loop 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 loop is OPERABLE and in operation.
- The shutdown cooling pump may be remaved 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 loop is OPERABLE.
- The shutdown cooling mode loop may be removed from operation during hydrostatic testing.
LIMERICK - UNIT 1 3/4 4-26 Amendment No. 97
b h
i REFUELING OPERATIONS
~
~ 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation
- with at least:
a.
One OPERABLE RHR heat exchanger.
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:
a.
With no RHR shutdown cooling mode loop OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 availabilty of at least one alternate method capable of decay heat removal.
Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
With no RHR shutdown cooling mode loop in operation, within I hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
SURVEILLANCE RE0VIREMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal system or 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 />.
i
- 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.
3 LIMERICK - UNIT 1 3/4 9-17 Amendment No. 97 t
REFUELING OPERATIONS L
LOW WATER LEVEL LINITING CONDITION FOR OPERATION-T 0
3.9.11.2 Two shutdown cooling mode loop of the residual heat removal. (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with
.each loop consisting of at least:
a.
b.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
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 less than the above required shutdown cooling mode loops of the
'RHR system OPERABLE, 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 i'
method capable of decay heat removal for each inoperable RHR shut-down cooling mode loop.
b.
With no RHR shutdown cooling mode loop in operation, within I hour i
establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
SURVEILLANCE REOUIREMENTS 3
l 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified to be in operation and circulating i
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 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.
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LIMERICK - UNIT 1 3/4 9-18 Amendment No. 97
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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 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__S.TRUCTURAL INTEGRITY l
l The inspection programs for ASME Code Class 1, 2, and 3 components ensure that i
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)(1). Additionally, the Inservice Inspection Program conforms to the i
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 RESIOUAL HEAT REMOVAL A single shutdown cooling mode loop provides sufficient heat removal capability for removing core decay heat and mixing to assure accurate temperature indication, however, single failure considerations require that two loops be OPERABLE or that alternate methods capable of decay heat removal be verified available by either 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 an alternate method of coolant mixing be operational.
v LIMERICK - UNIT 1 B 3/4 4-6 Amendment No.
49, 97
i REFUELING' OPERATIONS BASES 3/4.9.6 REFbELING 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 contro. 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 POOL 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 23 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.
3/4.9.3 ind 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAG E
>00L 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 withdrawn.
3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION I
The requirements that at least one residual heat removal loo) be OPERABLE or that an alternate method capable of decay heat removal be ver fied available by either calculation (which includes a review of com)onent and system availability to verify that an alternate decay heat removal method ns available) or by demonstration, and that an alternate method of coolant mixing be operational 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 )revent stratification of the poison in the event it becomes necessary to actuate tie standby liquid control system.
1 The requirement to have two shutdown cooling mode loops 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 resid-ual 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 a failure of the operating RHR loop, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
LIMERICK - UNIT 1 B 3/4 9-2 Amendment No.SS, 97
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UNITED STATCS NUCLEAR REGULATORY COMMISSION i
- ' ' ^
E Ei WASHINGTON, D.C. 20066 4 001 N
df 4*****4 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-85 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated August 31, 1994, as supplemented by letter dated-July 3, 1995, 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; t
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 i
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.
t i
[
5 9
- J 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in.the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Specifications The Tei.hnical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
61, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
This license amendment is effective as of its 'date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
i L a/.84./-
MJohnF.Stolz, Director I
Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
r Changes to the Technical Specifications i
Date of Issuance: July 18, 1995 t
l i
4 l
p I
ATTACHMENT TO LICENSE AMENDMENT NO. 61 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.
Remove Insert j
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 I
B S/4 4-6 8 3/4 4-6 B 3/4 9-2 B 3/4 9-2 t
1 e.
- 3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.1 Two* shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation ** ***
with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.
ACTION:
a.
With less than the above required RHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status 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 /> 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 RHR shutdown cooling mode loop. 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 />.****
i b.
With no RHR shutdown cooling mode loop in operation, immediately initiate corrective action to return at least one loop to operation as soon as possible. Within I hour establish reactor coolant circu-lation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.
SURVE!LLANCE REQUIREMENTS 4.4.9.1 At least one shutdown cooling mode loop of the residual heat removal system or 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 />.
- 0ne RHR shutdown cooling mode loop 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 loop 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 loop is OPERABLE.
v
- The RHR shutdown cooling mode loop may be removed from operation during 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. 61
/
- COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two* shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation ** ***
with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY: OPERATIONAL CONDITION 4.
ACTION:
a.
With less than the above required RHR shutdown cooling mode loops OPERABLE, 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 l
of decay heat removal for each inoperable RHR shutdown cooling mode loop.
b.
With no RHR shutdown cooling mode loop in operation, within I hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.
SVRVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or 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 />.
- 0ne RHR shutdown cooling mode loop 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 loop 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 loop is OPERABLE.
- The shutdown cooling mode loop may be removed from operation during hydrostatic testing.
)
l LIMERICK - UNIT 2 3/4 4-26 Amendment No. 61
C y
REFUELING OPERATIONS
+ 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL L
LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation
- with at least:
a.
One OPERABLE RHR heat exchanger.
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:
a.
With no RHR shutdown cooling mode loop OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 availabilty l
of at least one altern.te method capable of decay heat removal.
Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
With no RHR shutdown cooling mode loop in operation, 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 j
monitor reactor coolant temperature at least once per hour.
SURVEILLANCE RE0VIREMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal system or 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 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.
i e
1 LIMERICK - UNIT 2 3/4 9-17 Amendment No. 61
e REFUELING OPERATIONS
LOW WATER LEVEL t
LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
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 e
reactor pressure vessel flange.
ACTION:
a.
With less than the above required shutdown cooling mode loops of the RHR system GPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 l
method capable of decay heat removal for each inoperable RHR shut-down cooling mode loop.
b.
With no RHR shutdown cooling mode loop in operation, within I hour
[
establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
SURVEILLANCE RE0VIREMENTS 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal system or 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 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.
i LIMERICK - UNIT 2 3/4 9-18 Amendment No. 61
t, i
f REACTOR' COOLANT SYSTEM l
4
,~aASES l
3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 1
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 l
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 j
minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges.
i 3/4.4.8 STRUCTURAL INTEGRITY I
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 j
level throughout the life of the plant.
i Components of the reactor coolant system were designed to provide access to j
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 i
specific written relief has been granted by the NRC pursuant to 10 CFR
'l 50.55a(g)(6)(1). Additionally, the Inservice Inspection Program conforms to the 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.
j 3/4.4.9 RESIDUAL HEAT REMOVAL l
A single shutdown cooling mode loop provides sufficient heat removal capability for removing core decay heat and mixing to assure accurate temperature indication, however, single failure considerations require that two loops be OPERABLE or that alternate methods capable of decay heat removal be verified
'i available by either calculation (which includes a review of component and system.
I availability to verify that an alternate decay heat removal method is available) or by demonstration, and that an alternate method of coolant mixing be' operational.
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i LIMERICK - UNIT 2 B 3/4 4-6 Amendment No. 12, 61 l
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j REFUELING 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 assem(blies 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 L
excessive lifting force in the event they-are inadvertently engaged during being loaded into a unrodde)d cell. inadvertent criticality will not occur due to fuel-lifting operations, and (4 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL 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 ass)embly, 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.
3/4.9.1 anc 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAG ! POOL 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 ROD 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 withdrawn.
3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal' loo) be OPERABLE or. that an alternate method capable of decay heat removal be ver< fied available by l
either calculation (which includes a review of com>onent and system availability to j
verify that an alternate decay heat removal method < s available) or by demonstration, and that an alternate method of coolant mixing be operational 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 shutdown cooling mode loops 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 resid-ual 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 a failure of the operating RHR loop, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
LIMERICK - UNIT 2 B 3/4_9-2 Amendment No. 50, 61
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