ML17165A031
| ML17165A031 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/06/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17165A032 | List: |
| References | |
| NUDOCS 9907140024 | |
| Download: ML17165A031 (41) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPRL INC.
4 ALLEGHENYELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.
182 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the,amendment filed by PP8L, Inc., dated November 26, 1997, which was superseded by letter dated June 1, 1998, as supplemented by letters dated October 30, 1998, March 29, 1999, April20, 1999, and May 28, 1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the 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 willbe conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment willnot 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.
9907140624 990706 PDR ADGCK 05000387 P
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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 and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 182 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPLL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORYCOMMISSION S. Singh Bajwa, Chief, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 6, 1999
ATTACHMENTTO LICENSE AMENDMENTNO.
FACILITYOPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE 3.7-2 307 3 B 3.7-2 B 3.7-3 B 3.7-4 B 3.7-5 B 3.7-6 B 3.7-7 INSERT 3.7-2 37-3'~
B 3.7-2 B 3.7-3 B 3.7-4 B 3.7-5 B 3.7-6 B 3.7-7
HRSW System and UHS 3.7.1 ACTIONS (continued)
CONDITION B.
Both Unit 1 RHRSW subsystems inoperable.
REQUIRED ACTION B. 1 Restore one Unit 1 RHRSW subsystem to OPERABLE status.
COMPLETION TIME 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from discovery of'ne or both Unit 2 RHRSW subsystems not capable of supporting associated Unit 1 RHRSW subsystem AND 7 days C.
Required Action and associate'd Completion Time not met.
OR UHS inoperable C.l Be in MODE 3.
AND C.2 Be in MODE 4.
12-hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the water level is greater than or equal to 678 feet 1 inch above Mean Sea Level.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
SUSQUEHANNA - UNIT 1 TS / 3.7-2 Amendment $78, 182
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'CTIONS (continued)
SURVEILLANCE FREQUENCY SR 3.7.1.2 Verify the average water temperature of the UHS is:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a.
NOTE Only applicable with both units in MODE 1 or 2, or with either unit'in MODE 3 for less than twelve (12) 'hours..
c 85'F; or b.
NOTE Only applicable when either unit has been in MODE 3 for at least twelve (12).
hours but not more than twenty-four (24) hours.
s 87'F: or C.
NOTE Only applicable when either unit has been in MODE 3 for at least twenty-four (24) hours.
s 88'F.
SR 3.7.1.3 Verify each RHRSW manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.-
31 days SUSQUEHANNA - UNIT 1 TS / 3.7-3 Amendment 478, 182
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BASES RSW System and UHS B 3.7.1 APPLICABLE SAFETY ANALYSE (continued) following a LOCA.
The ability of the RHRSW System to support long term cooling of the reactor or primary containment is discussed in the FSAR. Chapters 6 and 15 (Refs.
2 and, 3, respectively).
These analyses explicitly assume that the RHRSW System will provide adequate cooling support to the equipment requi red for safe shutdown.
These analyses include the evaluation of the long term primary containment response after a design basis LOCA.
The safety analyses for long term cooling were'erformed for various combinations of RHR System failures.
The worst case single failure that would affect the performance of the RHRSW System is any failure that would disable one subsystem of the RHRSW System.
As discussed in the
- FSAR, Section 6.2.2 (Ref. 2) for these analyses.
manual initiation of the OPERABLE RHRSW subsystem and the associated RHR System is assumed to occur 30 minutes after a DBA.'n this case.
the maximum suppression chamber water temperature and pressure are analyzed to be below the design temperature of 220'F and maximum allowable pressure of 53 psig.
The RHRSW System, together with the UHS, satisfy Criterion 3 of the NRC Policy Statement.
(Ref.4)
LCO Two RHRSW subsystems are required to be OPERABLE to provide the required redundancy to ensure that the system functions to remove post ac'cident heat loads.
assuming the worst case single active failure occurs coincident with the loss of offsite power.
An RHRSW subsystem is considered OPERABLE when:
a.
C.
One pump is OPERABLE; and An OPERABLE flow path is capable of taking suction from the UHS and transferring the water to the RHR heat exchanger and returning it to the UHS at the assumed flow rate.
-The OPERABILITY of the UHS is based on having a minimum water level at the overflow weir of 678 feet 1 inch above mean sea level and a maximum water temperature of 85'F:
unless either unit is in MODE 3. If a unit enters MODE 3.
(continued)
SUSQUEHANNA - UNIT 1 TS /
B 3.7-2.
Revision 1
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HRSW System and UHS B 3.7.1 BASES (continued)
LCO (continued)
APPLICABILITY the time of entrance into this condition determines the appropr,iate maximum ultimate heat sink fluid temperature.
If the earliest unit to enter NODE 3 has been in that condition for less than twelve {12) hours, the peak temperature to maintain OPERABILITY of the ultimate heat sink remains at 85'F.
If either unit has been in NODE 3 for more than twelve (12) hours but less than twenty-four (24)
- hours, the OPERABILITY temperature of the ultimate heat sink becomes 87 F. If either unit has been in MODE 3 for twenty-four (24) hours or more. the OPERABILITY temperature of the ultimate heat sink becomes 88'F.
This OPERABILITY definition is supported by analysis and evaluations performed.in accordance with the guidance given in Regulatory Guide 1.27.
In MODES 1, 2, and 3. the RHRSM System and the UHS are required to be OPERABLE to support the OPERABILITY of the RHR System for primary containment cooling (LCO 3.6.2.3, "Residual Heat Removal (RHR) Suppression Pool Cooling," and LCO 3.6.2.4, "Residual Heat Removal (RHR) Suppression Pool Spray" ) and decay heat removal (LCO 3.4.8, "Residual Heat Removal
{RHR) Shutdown Cooling System-Hot Shutdown" ).
The Applicability is therefore consistent with the requirements of these systems.
In NODES 4 and 5, the OPERABILITY requirements of the RHRSM System are determined by the RHR shutdown cooling subsystem(s) it supports (LCO 3.4.9, "Residual Heat Removal (RHR) Shutdown Cooling System
- Cold Shutdown";
LCO 3.9.7, "Residual Heat Removal (RHR) - High Water Level"; and LCO 3.9.8, "Residual Heat Removal (RHR) - Low Mater Level").
In NODES 4 and 5, the OPERABILITY requirements of the UHS is determined by the systems it supports.
{continued)
SUSQUEHANNA - UNIT 1 TS / 8 3.7-3 Revision 1
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HRSW System and UHS B 3.7.1 BASES (continued)
ACTIONS The-ACTIONS are modified by a Note indicating that the applicable Conditions of LCO 3.4.8.
be entered and Required Actions taken if the inoperable RHRSW subsystem results in inoperable RHR shutdown cooling (SDC) (i.e., both the Unit 1 and Unit 2 RHRSW pumps in a loop are inoperable resulting in the associated RHR SDC system being inoperable).
This is an
'. exception to LCO 3.0.6 because the Required Actions of LCO 3.7. 1 do not adequately compensate for the loss of RHR.SDC Function (LCO 3.4.8).
. ~1 Required Action A. 1 is intended to ensure that appropriate actions are taken if one Unit 1 RHRSW subsystem is inoperable.
Although designated and operated as a unitized
- system, the associated Unit 2 subsystem is directly connected to a common header which can supply the associated RHR heat exchanger in either unit.
The lJnit 2 subsystems are considered capable of supporting Unit 1 RHRSW subsystem when the Unit 2 subsystem is OPERABLE and can provide the assumed flow to the Unit 1 heat exchanger.
A Completion time.of 7 days, when one or both Unit 2 RHRSW subsystems are not capable of supporting the Unit 1 RHRSW subsystems.
is allowed to restore the Unit 1 RHRSW subsystem to OPERABLE status.
In this configuration. the remaining OPERABLE Unit 1 RHRSW subsystem is adequate to perform the RHRSW heat removal function.
However, the overal) reliability is reduced because a single failure in the OPERABLE RHRSW subsystem could result in loss of RHRSW function.
The Completion Time is based on the redundant RHRSW capabilities afforded by the OPERABLE subsystem and the low probability of an event occurring requiring RHRSW during this period.
With one RHRSW subsystem inoperable, and both of the Unit 2 RHRSW subsystems capable of supporting their respective Unit 1 RHRSW subsystems, the design basis cooling capacity for both units can still be maintained even considering a
single active failure.
However, the configuration does reduce the overall reliability of the RHRSW System.
Therefore, provided both of the Unit 2 subsystems remain capable of supporting their respective Unit 1 RHRSW subsystems, the inoperable RHRSW subsystem must be restored to OPERABLE status within 30 days.
The 30 day Completion Time is based on the remaining RHRSW System heat removal capability.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.7-4 Revision 1
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IHRSW System and llHS B 3. 7. 1
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BASES (conti nued)
ACTIONS B.l Required Action B.1 is intended to ensure that appropriate actions are taken if both Unit 1 RHRSW subsystems are inoperable.
Although designated and operated as a unitized
- system, the associated Unit 2 subsystem is directly connected to a common header which can supply the associated RHR heat exchanger in either unit.
With both Unit 1 RHRSW subsystems inoperable not caused by the inoperability of two Unit 1 RHRSW Pumps (e.g.. both subsystems with inoperable flow paths, or one subsystem with an inoperable pump and one subsystem with an inoperable flow path), the RHRSW System is not capable of performing its intended function.
At least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time for restoring one RHRSW subsystem to OPERABLE status, is based on the Completion Times provided f'r the RHR suppression pool spray function.
With both Unit 1 RHRSW subsystems inoperable, and both of the Unit 2 RHRSW subsystems capable of supporting their respective Unit 1 RHRSW subsystem, if no additional failures occur which impact the RHRSW System.
the remaining OPERABLE Unit 2 subsystems and flow paths provide adequate heat removal capacity following a design basis LOCA.
However.
capability for this alignment is not assumed in long term containment response analysis and an additional single failure in the RHRSW System could reduce the system capacity below that assumed in the safety analysis.
Therefore, continued oper ation is permitted only for a limited time.
One inoperable subsystem is required to be restored to OPERABLE status within 7 days.
The 7 day Completion Time for restoring one inoperable RHRSW subsystem to OPERABLE status is based on engineering judgment. considering the level of redundancy provided, and the low probability of a DBA with concurrent worst case single failure.
C.1 and C.2 If the RHRSW subsystems cannot be restored to OPERABLE status within the associated Completion Times, or the UHS is determined to be inoperable, the unit must be placed in a NODE in which the LCO does not apply.
To achieve this
- status, the unit must be placed in at least NODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in NODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The allowed (continued)
SUSQUEHANNA - UNIT 1 TS / 8 3.7-5 Revision 1
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RSW System and UHS B 3.7.1 BASES (continued)
ACTIONS C.l and C.2 (continued)
Completion Times are reasonable, based on operating experience, to reach the,required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE REQUIREMENTS SR 3.7.1.1 This SR verifies the water level to be sufficient for the roper operation of the RHRSW pumps (net positive suction ead and pump vortexing are considered in determining this limit).
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is based on operating experience related to trending of the parameter variations during the applicable NODES.
SR 3.7.1.2 Verification of the UHS temperature, which is the arithmetical average of the UHS temperature near the
- surface, middle and bottom levels, ensures that the heat removal capability of the ESW and RHRSW Systems are within the assumptions of the DBA analysis.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience related to trending of the parameter variations during the applicable NODES.
SR 3.7.1.3 Verifying the correct alignment for each manual, power
- operated, and automatic valve in each RHRSW subsystem flow path provides assurance that the proper flow paths will exist for RHRSW operation.
This SR does not apply to valves that are locked. sealed, or otherwise secured in position, since these valves are verified to be in the correct position pr ior to locking, sealing,'or,securing.
A valve is also al.lowed to be in the nonaccident position, and yet considered in the correct position. provided it can be realigned to its accident position.
This is acceptable because the RHRSW System is a manually initiated system.
(continued)
SUSQUEHANNA - UNIT 1 TS / 8 3.7-6 Revision 1
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IRSW System and UHS 8 3. 7. 1 BASES (conti nued)
SURVEILLANCE REQUIREMENTS (continued)
SR 3.7. 1.3 (continued)
A This SR does not require any testing or valve manipulation:
rather, it involves verification that those valves capable of being mispositioned are in the correct position.
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.
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The 31 day Frequency is based on engineering. judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.
REFERENCES 1.
FSAR, Section 9.2.6.
2.
FSAR, Chapter 6.
3.
FSAR, Chapter 15.
4.
Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
SUSQUEHANNA - UNIT 1 TS / 8 3.7-7 Revision 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 PP8aL INC.
ALLEGHENYELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 156 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A. The application for the amendment filed by the PP&L, Inc., dated November 26, 1997, which was superseded by letter dated June 1, 1998, as supplemented by letters dated October 30, 1998, March 29, 1999, April 20, 1999, and May 28, 1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B. The facilitywilloperate in conformity with the application, the provisions of the Act, and the 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 willbe conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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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- 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 the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
156 and the Environmental Protection Pla'n contained in Appendix B, are hereby incorporated in the license. PP8L 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 REGULATORYCOMMISSION S. Singh Bajwa, Chief,Section I
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
july 6, f 999
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ATTACHMENTTO LICENSE AMENDMENTNO.
FACILITYOPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE 307-2 307 3 B 3.7-2 B 3.7-3 B 3.7-4 B 3.7-5 B 3.7-6 B 3.7-7 INSERT 3.7-2 317 3 B 3.7-2 B 3.7-3 B 3.7-4 B 3.7-5 B 3.7-6 B 3.7-7
RHRSW System and UHS 3 7.1 ACTIONS (continued)
CONDITION B.
Both Unit 2 RHRSW subsystems inoperable.
1 C
REQUIRED ACTION B.l Restore one Unit 2 RHRSM subsystem to OPERABLE status.
COMPLETION TINE 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from discovery of one or both Unit 1 RHRSW subsystems not capable of supporting associated Unit 2 RHRSW subsystem AND 7 days C.
Required Action and associated Completion Time not met.
OR UHS inoperable C.l Be in NODE 3.
AND C.2 Be in NODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.1.1 Verify the water level is greater than or equal to 678 feet 1 inch above Mean Sea Level.
FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
SUSQUEHANNA - UNIT 2 TS / 3.7-2 Amendment 464, i56
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HRSW System and UHS 3.7.1 ACTIONS (continued)
SURVEILLANCE FREQUENCY SR 3.7.1.2 Verify the average water temperature of the UHS is:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a.
NOTE Only applicable with both units in NODE 1 or 2, or with either unit in NODE 3 for less than twelve (12) hours.
~ 85'F or b.
NOTE Only applicable when either unit has been in NODE 3 for at least twelve (12) hours but not more than twenty-four (24) hours.
~ 87'F; or C.
NOTE Only applicable when either unit has been in NODE 3 for at least twenty-four (24) hours.
~ 88'F.
SR 3.7.1.3 Verify each RHRSM manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.
31 days SUSQUEHANNA - UNIT 2 TS / 3.7-3 Amendment 4~4, 1 56
BASES HRSW System and UHS B 3.7.1 APPLICABLE SAFETY ANALYSE (continued) following a LOCA.
The ability of the RHRSW System to support long term cooling of the reactor or primary
- ~
containment is discussed in the FSAR, Chapters 6 and 15 (Refs.
2 and 3, respectively).
These analyses.explicitly assume that the RHRSW System will provide adequate cooling support to the equipment required for safe shutdown.
These analyses include the evaluation of the long term primary containment response after a design basis LOCA.
The safety analyses for long term cooling were performed f'r various combinations of RHR System failures.
The worst case single failure that would affect the perf'ormance of'he RHRSW System is any failure that would disable one subsystem of the RHRSW System.
As discussed in the
- FSAR, Section 6.2.2 (Ref. 2) for these analyses, manual initiation of'he OPERABLE RHRSW subsystem and the associated RHR System is assumed to occur 30 minutes after a
DBA.
In this
- case, the maximum suppression chamber water temperature and pressure are analyzed to be below the design temperature of 220'F and maximum allowable pressure of 53 psig.
The RHRSW System, together with the UHS. satisfy Criterion 3 of the NRC Policy Statement.
(Ref.4)
LCO Two RHRSW subsystems are required to be OPERABLE to provide the required redundancy to ensure that the system functions to remove post accident heat loads.
assuming the worst case single active failure occurs coincident with the loss of offsite power.
An RHRSW subsystem is considered OPERABLE when:
a.
One pump is OPERABLE; and b.
An OPERABLE flow path is capable of taking suction from the UHS and transferring the water to the RHR
'eat exchanger and returning it to the UHS at the assumed flow rate, and c.
The OPERABILITY of the UHS is based on having a minimum water level at the overflow weir of 678 feet 1 inch above mean sea level and a maximum water temperature of 85'F:
(continued)
SUSQUEHANNA - UNIT 2 TS /
B 3.7-2 Revision 1
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BASES (continued)
HRSW System and UHS B 3.7.1 LCO (continued)
APPLICABILITY unless either unit is in MODE 3. If a unit enters MODE 3.
the time of entrance into this condition determines the approp'riate maximum ultimate heat sink fluid temperature.
If the earliest unit to enter MODE 3 has been in that condition for less than twelve (12) hours. the peak temperature to maintain OPERABILITY of the ultimate heat sink remains at 85'F.
If either unit has been in MODE 3 for more than twelve (12) hours but less than twenty-four (24) hours, the OPERABILITY temperature of the ultimate heat sink becomes 87'F.
If either unit has been in MODE 3 for twenty-four (24) hours or more, the OPERABILITY temperature of the ultimate heat sink becomes 88 F.
This OPERABILITY definition is supported by analysis and evaluations performed in accordance with the guidance given in Regulatory Guide 1.27.
In MODES 1, 2, and 3, the RHRSW System and the UHS are required to be OPERABLE to suppoi"t the OPERABILITY of the RHR System f'r primary containment cooling (LCO 3.6.2.3, "Residual Heat Removal (RHR) Suppression Pool Cooling," and LCO 3.6.2.4, "Residual Heat Removal (RHR) Suppression Pool Spray" ) and decay heat remova1
{LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown" ).
The Applicability is therefore consistent with the requirements of these systems.
In MODES 4 and 5. the OPERABILITY requirements of the RHRSW System are determined by the RHR shutdown cooling subsystem(s) it supports (LCO 3.4.9, "Residual Heat Removal (RHR) Shutdown Cooling System
- Cold Shutdown":
LCO 3.9.7, "Residual Heat Removal (RHR) - High Water Level"; and LCO 3.9.8, "Residual Heat Removal (RHR) - Low Water Level").
In MODES 4 and 5, the OPERABILITY requirements of the UHS is determined by the systems it supports.
(continued)
SUSQUEHANNA - UNIT 2 TS / B 3.7-3 Revision 1
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HRSW System and UHS B 3.7.1 BASES (continued)
ACTIONS The ACTIONS are modified by a Note indicating that the applicable Conditions of LCO 3.4.8, be entered and Required Actions taken if the inoperable RHRSM subsystem results in inoperable RHR shutdown cooling (SDC) (i.e., both the Unit 1 and Unit 2 RHRSM pumps in a loop are inoperable resulting in the associated RHR SDC system being inoperable).
This is an exception to LCO 3.0.6 because the Required Actions of LCO 3.7. 1 do not adequately compensate for the loss of RHR SDC Function (LCO 3.4.8).
A,l Required Action A. 1 is intended to ensure that appropriate actions are taken if one Unit 2 RHRSW subsystem is inoperable.
Although designated and operated as a unitized
- system, the associated Unit 1 subsystem is directly connected to a common header which can supply the associated RHR heat exchanger in either unit.
The Unit 1 subsystems are considered capable of supporting Unit 2 RHRSW subsystem when the Unit 1 subsystem is OPERABLE and can provide the assumed flow to the Unit 2.heat exchanger.
A Completion time of 7 days.
when one or both Unit 1 RHRSW subsystems are not capable of supporting the Unit 2 RHRSW subsystems, is allowed to restore the Unit 2 RHRSM subsystem to OPERABLE status.
In this configuration, the remaining OPERABLE Unit 2 RHRSW subsystem is adequate to perform the RHRSM heat removal function.
However, the overall reliability is reduced because a single failure in the OPERABLE RHRSM subsystem could result in loss of RHRSW function.
The Completion Time is based on the redundant RHRSM capabilities afforded by the OPERABLE subsystem and the low probability of an event occurring requiring RHRSW during this period.
With one RHRSW subsystem inoperable, and both of the Unit 1 RHRSW subsystems capable of supporting their respective Unit 2 RHRSW subsystems, the design basis cooling capacity for both units can still be maintained even considering a
single active failure.
However, the configuration does reduce the overall reliability of the RHRSW System.
Therefore, provided both of the Unit 1 subsystems remain capable of supporting their respective Unit 2 RHRSW subsystems, the inoperable RHRSM subsystem must be restored to OPERABLE status within 30 days.
The 30 day Completion Time is based on the remaining RHRSW System heat removal capability.
(continued)
SUSQUEHANNA - UNIT 2 TS I B 3.7-4 Revision 1
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RSW System and UHS B 3.7.1 BASES (continued)
ACTIONS B.1 Required Action B.1 is intended to ensure that appropriate actions are taken if both Unit 2 RHRSW subsystems are inoperable.
Although designated and operated as a unitized
- system, the associated Unit 1 subsystem is directly connected to a common header which can supply the associated RHR heat exchanger.
in either unit.
With both Unit 2 RHRSW
. subsystems inoperable not cause'd by the inoperability of two
, Unit 2 RHRSW Pumps (e.g., both subsystems with inoperable flow paths, or one subsystem with an inoperable pump and one subsystem with an inoperable flow path). the RHRSW System is not capable of performing its intended function.
At least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time for restoring one RHRSW subsystem to OPERABLE status, is based on the Completion Times provided for the RHR suppression pool spray function.
With both Unit 2 RHRSW subsystems inoperable, and both of the Unit 1 RHRSW subsystems capable of supporting their respective Unit 2 RHRSW subsystem, if no additional fai lures occur which impact the RHRSW System, the remaining OPERABLE Unit 1 subsystems and flow paths provide adequate heat removal capacity following a design basis LOCA.
However.
capability for this alignment is not assumed in long term containment response analysis and an additional single failure in the RHRSW System could reduce the system capacity below that assumed in the safety analysis.
Therefore, continued operation is permitted only for a limited time.
One inoperable subsystem is required to be restored to OPERABLE status within 7 days.
The 7 day Completion Time for restoring one inoperable RHRSW subsystem to OPERABLE status is based on engineering judgment.
considering the level of redundancy provided, and the low probability of a DBA with concurrent worst case single failure.
C.1 and C.2 If the RHRSW subsystems cannot be restored to OPERABLE status within the associated Completion Times, or the UHS is determined to be inoperable.
the unit must be placed in a NODE in which the LCO does not apply.
To achieve'this status.
the unit must be placed in at least NODE 3 within
'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and in NODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The allowed
{continued)
SUSQUEHANNA - UNIT 2 TS / 8 3.7-5 Revision 1
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HRSW System and UHS 8 3.7.1 BASES (continued)
ACTIONS C.l and C.2 (continued)
Completion Times are reasonable, based on operating
'xperience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE REQUIREMENTS SR 3.7.1.1 This SR verifies the water level to be sufficient for the.
roper operation of the RHRSW pumps (net positive suction ead and pump vortexing are considered in determining this limit).
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is based on operating experience related to trending of the parameter variations during the applicable NODES.
SR 3.7.1 2
Verification of the UHS temperature, which is the arithmetical average of the UHS temperature near the
- surface, middle and bottom levels, ensures that the heat removal capability of the ESW and RHRSW Systems are within
~
the assumptions of the DBA analysis.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience related to trending of the parameter variations during the applicable NODES.
SR 3.7.1.3 Verifying the correct alignment for each manual, power
- operated, and automatic valve in each RHRSW subsystem flow path provides assurance that the proper flow paths will exist for RHRSW operation.
This SR does not apply to valves that are locked, sealed, or otherwise secured in position.
since.these valves are verified to be in the correct position prior to locking, sealing, or securing.
A valve is also allowed to be in the nonaccident position, and yet considered in the correct position, provided it can be realigned to its accident position.
This is acceptable because the RHRSW System is a manually initiated system.
SUSQUEHANNA - UNIT 2 TS / 8 3.7-6 (continued)
Revision 1
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HRSW System and UHS B 3.7.1 BASES (continued)
SURVEILLANCE REQUIREHENTS (continued)
SR 3.7.1.3 (continued)
This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.
The 31 day Frequency is based on engineering judgment, is consistent with the procedural control's governing valve operation, and ensures correct valve positions.
REFERENCES 1.
FSAR, Section 9.2.6.
2.
FSAR, Chapter 6.
3.
FSAR, Chapter 15.
4.
Final Policy Statement on Technical Specifications Improvements, July 22.
1993 (58 FR 39132).
SUSQUEHANNA - UNIT 2 TS /
B 3.7-7 Revision 1
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