PLA-6141, Request for an Amendment to the Technical Specifications: Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities Using the Consolidated Line Item Improvement Process (CLIIP)
| ML071710440 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/08/2007 |
| From: | Gannon C J Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6141 | |
| Download: ML071710440 (24) | |
Text
N T.C. J. Gannon Vice President Nuclear Operations U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP 1 -17 Washington, DC 20555 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3050 Fax 570.542.1504 cjgannon@pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 292 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 261 TO LICENSE NPF-22: REQUEST FOR ADOPTION OF TSTF-484, REV. 0, "USE OF TS 3.10.1 FOR SCRAM.TIME TESTING ACTIVITIES" USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)PLA-6141 Docket Nos. 50-387 and 50-388 In accordance with the provisions of 10.CFR 50.90, PPL Susquehanna, LLC is submitting a request for an amendment to the Technical Specifications for Susquehanna Steam Electric Station Units I and 2.The proposed amendment would revise LCO 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 200 'F as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in c0njunction with an inservice leak or hydrostatic test, while considering:
operational conditions to be in Mode 4. The changes are consistent with NRC approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-484, "Use of TS 3.10.1 for Scram Time Testing Activities." The availability of the TS 3. 10.1 revision was announced in the Federal Register on October 27, 2006 (71 FR 63050) as part of the consolidated line item improvement process (CLUP).These proposed changes have been reviewed by both the Plant Operations Review Committee and the Susquehanna Review Committee.
Attachment 1 provides an evaluation of the proposed change. Attachment 2 provides the existing Technical Specifications pages marked-up to show the proposed change. Document Control Desk PLA-6141 Attachment 3 provides the existing Bases pages marked-up to show the proposed change.No regulatory commitments are made in this submittal.
PPL Susquehanna, LLC requests approval of the proposed License Amendment by October 1, 2007 with the amendment being implemented within 30 days following approval.In accordance with 10 CFR 50.9 1(b), PPL Susquehanna, LLC is providing the Commonwealth of Pennsylvania with a copy of this proposed License Amendment request.If you have any questions regarding this submittal, please contact Mr. Cornelius T. Coddington at (610) 774-4019.I declare under penalty of perjury under the laws of the United States of America that I am authorized by PPL Susquehanna, LLC to make this request and that the foregoing is true and correct.Executed on: 4 4 c7 C. J.Gangno Attachments:
Attachment 1 -Evaluation of the Proposed Change Attachment 2 -Proposed Technical Specification Changes Units 1 & 2, (Mark-ups)
Attachment 3 -Proposed Technical Specification Bases Changes Units I & 2, (Mark-ups
-For Information Only)cc: NRC Region I Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Sr. Project Manager Mr. R. R Janati, DEP/BRP Attachment 1 to PLA-6141 Evaluation of the Proposed Change 1.0 Description
2.0 Proposed
Change 3.0 Background
4.0 Technical
Analysis 5.0 Regulatory Safety Analysis 5.1 No Significant Hazards Determination
5.2 Applicable
Regulatory Requirements/Criteria
6.0 Environmental
Consideration
7.0 References
Attachment 1 to PLA-6141 Page 1 of 2 EVALUATION OF PROPOSED CHANGE
1.0 DESCRIPTION
The proposed amendments would revise LCO 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 200'F as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4. This change is consistent with NRC approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-484, "Use of TS 3.10.1 for Scram Time Testing Activities." The availability of the TS 3.10.1 revision was announced in the Federal Register on October 27, 2006 (71 FR 63050) as part of the consolidated line item improvement process (CLIIP).
2.0 PROPOSED CHANGE
Consistent with the NRC approved Revision 0 of TSTF-484, the proposed TS changes include a revised TS 3.10.1, "Inservice Leak and Hydrostatic Testing Operation." Proposed revisions to the TS Bases are also included in this application.
Adoption of the TS Bases associated with TSTF-484, Revision 0 is an integral part of implementing these TS amendments.
The changes to the affected TS Bases pages will be incorporated in accordance with the TS Bases Control Program.This application is being made in accordance with the CLIIP. PPL Susquehanna, LLC is not proposing variations or deviations from the TS changes described in TSTF-484, Revision 0, or the NRC staff s model safety evaluation (SE) published on October 27, 2006 (71 FR 63050) as part of the CLIIP Notice of Availability.
3.0 BACKGROUND
The background for this application is adequately addressed by NRC Notice of Availability published on October 27, 2006 (71 FR 63050).4.0 TECHNICAL ANALYSIS PPL Susquehanna, LLC has reviewed the safety evaluation (SE) published on October 27, 2006, as part of the CLIIP Notice of Availability.
PPL Susquehanna, LLC has concluded that the technical justifications presented in the SE prepared by the NRC staff are applicable to Susquehanna Steam Electric Station Units 1 and 2 and therefore, Attachment 1 to PLA-6141 Page 2 of 2 justify these amendments for the incorporation of the proposed changes to the Susquehanna Steam Electric Station Units 1 and 2 Technical Specifications.
5.0 REGULATORY
SAFETY ANALYSIS 5.1 No Significant Hazards Consideration PPL Susquehanna, LLC has reviewed the no significant hazards determination published on August 21, 2006 (71 FR 48561) as part of the CLIIP Notice for Comment. The no significant hazards determination was made available on October 27, 2006 (71 FR 63050) as part of the CLIIP Notice of Availability.
PPL Susquehanna, LLC has concluded that the determination presented in the notice is applicable to Susquehanna Steam Electric Station Units I and 2 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).5.2 Applicable Regulatory Requirements/Criteria A description of the proposed TS change and its relationship to applicable regulatory requirements was provided in the NRC Notice of Availability published on October 27, 2006 (71 FR 63050).6.0 ENVIRONMENTAL EVALUATION PPL Susquehanna, LLC has reviewed the environmental evaluation included in the safety evaluation (SE) published on October 27, 2006 (71 FR 63050), as part of the CLIIP Notice of Availability.
PPL Susquehanna, LLC has concluded that the NRC staff's findings presented in that evaluation are applicable to Susquehanna Steam Electric Station Units I and 2 and the evaluation is hereby incorporated by reference for this application.
7.0 REFERENCES
- 1. Federal Register Notice, Notice of Availability published on October 27, 2006 (71 FR 63050)2. Federal Register Notice, Notice for Comment published on August 21, 2006 (71 FR 48561)3. TSTF-484 Revision 0, "Use of TS 3.10.1 for Scram Time Testing Activities" Attachment 2 to PLA-6141 Proposed Technical Specification Changes Units 1 & 2 (Mark-ups)
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)
PPL Rev. 7 1 3.7 PLANT SYSTEMS .............................................................................
TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ..........................................
TS/3.7-1 3.7.2 Emergency Service Water (ESW) System ........................................
3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System .................................................................
TS/3.7-6 3.7.4 Control Room Floor Cooling System .................................................
3.7-10 3.7.5 Main Condenser Offgas ....................................................................
3.7-13 3.7.6 Main Turbine Bypass System .......................................................
TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level .......................
..... 3.7-17 3.8 ELECTRICAL POWER SYSTEMS .....................................................
TS/3.8-1 3.8.1 AC Sources -Operating
.......................................................
TS/3.8-1 3.8.2 AC Sources -Shutdown ...............................................................
TS/3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .....................................
TS/3.8-20 3.8.4 DC Sources -Operating
...................................................................
3.8-23 3.8.5 DC Sources -Shutdown ...................................................................
3.8-29 3.8.6 Battery Cell Parameters
................................................................
TS/3.8-32 3.8.7 Distribution Systems -Operating
..................................................
TS/3.8-37 3.8.8 Distribution Systems -Shutdown ..................................................
TS/3.8-41 3.9 REFUELING OPERATIONS
...................................................................
3.9-1 3.9.1 Refueling Equipment Interlocks
.........................................................
3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock
.............................................
3.9-3 3.9.3 Control Rod Position .........................................................................
3.9-5 3.9.4 Control Rod Position Indication
.........................................................
3.9-6 3.9.5 Control Rod OPERABILITY
-Refueling
............................................
3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level ....................................
3.9-9 3.9.7 Residual Heat Removal (RHR) -High Water Level ..........................
3.9-10 3.9.8 Residual Heat Removal (RHR) -Low Water Level ...........................
3.9-13 3.10 SPECIAL OPERATIONS
....................................................................
TS/3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation
........................
TS/3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .............................................
3.10-4 3.10.3 Single Control Rod Withdrawal
-Hot Shutdown ...............................
3.10-6 3.10.4 Single Control Rod Withdrawal
-Cold Shutdown ..............................
3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal -Refueling
......................
3.10-13 3.10.6 Multiple Control Rod Withdrawal
-Refueling
....................................
3.10-16 3.10.7 Control Rod Testing-Operating
.........................................................
3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling
................................
3.10-20 4.0 DESIGN FEATURES ....................................................................................
4.0-1 4 .1 S ite Locatio n ........................................................................................
4 .0-1 4 .2 R eactor C ore .......................................................................................
4 .0-1 4 .3 F ue l S to rage ........................................................................................
4 .0-1 (continued)
SUSQUEHANNA
-UNIT 1 TS / TOC -3 Amendment 10, 2W, U5, 2,34 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for Mode 4 may be changed to 212 0 F, and operation considered not to be in MODE 3; and the requirements of LCO 3.4.9, "Residual Heat Removal (RHR) Shutdown Cooling System -Cold Shutdown," may be suspended to allow reactor coolant temperature
> 200°F: o For, te alow- performance of an inservice leak or hydrostatic test,* As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or* As a consequence of maintaining pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following LCOs are met: a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, 4, 5, 6, 7 and 8 of Table 3.3.6.2-1;
- b. LCO 3.6.4.1, "Secondary Containment";
- c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";
and d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." APPLICABILITY:
MODE 4 with average reactor coolant temperature
>200°F and < 212 0 F.SUSQUEHANNA
-UNIT 1 TS / 3.10-1 Amendment 474 1 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)
PPL Rev.1.0 USE AND APPLICATION
.............................................................................
1.1-1 1 .1 D e fin itio n s ............................................................................................
1 .1-1 1.2 Logical C onnectors
..............................................................................
1.2-1 1.3 C om pletion T im es ................................................................................
1.3-1 1.4 F req ue ncy ............................................................................................
1.4 -1 2.0 SAFETY LIMITS (SLs) .............................................................................
TS/2.0-1 2 .1 S L s .................................................................................................
T S /2 .0 -1 2 .2 S L V iolations
...................................................................................
T S /2 .0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
.........
TS/3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
.......................
TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ......................................................
3.1-1 3.1.1 Shutdown Margin (SDM) ...................................................................
3.1-1 3.1.2 Reactivity Anomalies
.........................................................................
3.1-5 3.1.3 Control Rod OPERABILITY
...............................................................
3.1-7 3.1.4 Control Rod Scram Times ............................................................
TS/3.1-12 3.1.5 Control Rod Scram Accumulators
.....................................................
3.1-15 3.1.6 Rod Pattern Control ..........................................................................
3.1-18 3.1.7 Standby Liquid Control (SLC) System ...............................................
3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ...............
TS/3.1-25 3.2 POWER DISTRIBUTION LIMITS ............................................................
3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) .................
3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) ..............................................
3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ...............................................
3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints
.............
3.2-7 3.3 INSTRUMENTATION
.............................................................................
3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation
........................
TS/3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation
..................................
3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM)Instrumentation
....................................................................
TS/3.3-15a 3.3.2.1 Control Rod Block Instrumentation
....................................................
3.3-16 3.3.2.2 Feedwater
-Main Turbine High Water Level Trip Instrum entation ...........................................................................
3.3-2 1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation
.........................
TS/3.3-23 3.3.3.2 Remote Shutdown System ...........................................................
TS/3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)Instrum entation ...........................................................................
3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)
Instrumentation
....................................
3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation
..........
TS/3.3-37 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation ...........................................................................
3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation
.............................
TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation
............................
3.3-63 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)System Instrumentation
..................................................................
3.3-67 (continued)
SUSQUEHANNA
-UNIT 2 TS / TOC -1 Amendment 1,V1, 1,5, 190, 1K2, 1,9, 202, 211 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)
PPL Rev.3.7 PLANT SYSTEMS .............................................................................
TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ..........................................
TS/3.7-1 3.7.2 Emergency Service Water (ESW) System ........................................
3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System .................................................................
TS/3.7-6 3.7.4 Control Room Floor Cooling System .................................................
3.7-10 3.7.5 Main Condenser Offgas ....................................................................
3.7-13 3.7.6 Main Turbine Bypass System .......................................................
TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level ...............................................
3.7-17 3.8 ELECTRICAL POWER SYSTEMS ....................................................
TS/3.8-1 3.8.1 AC Sources -Operating
..............................................................
TS/3.8-1 3.8.2 AC Sources -Shutdown ..............................................................
TS/3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ....................................
TS/3.8-23 3.8.4 DC Sources -Operating
...................................................................
3.8-26 3.8.5 DC Sources -Shutdown ...................................................................
3.8-34 3.8.6 Battery GeOl Parameters
...............................................................
TS/3.8-39 3.8.7 Distribution Systems -Operating
.................................................
TS/3.8-44 3.8.8 Distribution Systems -Shutdown ......................................................
3.8-50 3.9 REFUELING OPERATIONS
...................................................................
3.9-1 3.9.1 Refueling Equipment Interlocks
.........................................................
3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock
.............................................
3.9-3 3.9.3 Control Rod Position ...........
....... .....................
3.9-5 3.9.4 Control Rod Position Indication
.........................................................
3.9-6 3.9.5 Control Rod OPERABILITY
-Refueling
............................................
3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level ....................................
3.9-9 3.9.7 Residual Heat Removal (RHR) -High Water Level ..........................
3.9-10 3.9.8 Residual Heat Removal (RHR) -Low Water Level ...........................
3.9-13 3.10 SPECIAL OPERATIONS
...................................................................
TS/3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation
.......................
TS/3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .............................................
3.10-4 3.10.3 Single Control Rod Withdrawal
-Hot Shutdown ...............................
3.10-6 3.10.4 Single Control Rod Withdrawal
-Cold Shutdown ..............................
3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal -Refueling
......................
3.10-13 3.10.6 Multiple Control Rod Withdrawal
-Refueling
....................................
3.10-16 3.10.7 Control Rod Testing -Operating
.......................................................
3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test -Refueling
................................
3.10-20 4.0 DESIGN FEATURES .................................................................................
TS/4.0-1 4 .1 S ite Location .....................................................................................
T S /4 .0-1 4.2 R eactor C ore ....................................................................................
TS/4.0-1 4 .3 Fuel S torage .....................................................................................
T S /4.0-1 (continued)
SUSQUEHANNA
-UNIT 2 TS / TOC -3 Amendment 1,91, 1X8, 19%2, 241 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for Mode 4 may be changed to 212 0 F, and operation considered not to be in MODE 3; and the requirements of LCO 3.4.9, "Residual Heat Removal (RHR) Shutdown Cooling System -Cold Shutdown," may be suspended to allow reactor coolant temperature
> 200°F:* For, to rae" performance of an inservice leak or hydrostatic test, o As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or o As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following LCOs are met: a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, 4, 5, 6, 7 and 8 of Table 3.3.6.2-1;
- b. LCO 3.6.4.1, "Secondary Containment";
- c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";
and d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." APPLICABILITY:
MODE 4 with average reactor coolant temperature
>200 0 F and < 212 0 F.SUSQUEHANNA
-UNIT 2 TS / 3.10-1 Amendment 4-" 1 Attachment 3 to PLA-6141 Proposed Technical Specification Bases Changes Units 1 & 2 (Mark-ups
-For Information Only)
PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 B 3.10 SPECIAL OPERATIONS B 3.10.1 Inservice Leak and Hydrostatic Testing Operation BASES BACKGROUND The purpose of this Special Operations LCO is to allow certain reactor coolant pressure tests to be performed in MODE 4 with temperatures as high as 212°F when operational conditions or the metallurgical characteristics of the reactor pressure vessel (RPV) require the pressure testing at temperatures
> 200'F (normally corresponding to MODE 3) or to allow completing these reactor coolant pressure tests when the initial conditions do not require temperatures
> 200 0 F.Furthermore, the purpose is to allow continued performance of control rod scram time testing required by SR 3.1.4.1, SR 3.1.4.3 or SR 3.1.4.4 if reactor coolant temperatures exceed 200°F when the control rod scram time testing is initiated in conjunction with an inservice leak or hydrostatic test. These control rod scram time tests would be performed in accordance with LCO 3.10.4, "Single Control Rod Withdrawal
-Cold Shutdown," during MODE 4 operation.
Inservice hydrostatic testing and system leakage pressure tests required by Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Ref. 1) are performed prior to the reactor going critical after a refueling outage.Recirculation pump operation and a water solid RPV (except for an air bubble for pressure control) are used to achieve the neessaray necessary temperatures and pressures required for these tests. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T)limits required by LCO 3.4.10, "Reactor Coolant System (RCS)Pressure and Temperature (P/T) Limits." These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated vessel neutron fluence.With increased reactor vessel fluence over time, the minimum allowable vessel temperature increases at a given pressure.
Periodic updates to the RPV P/T limit curves are performed as necessary, based upon the results of analyses of irradiated surveillance specimens removed from the vessel. Hydrostatic and leak testing may eventually be required with minimum reactor coolant temperatures
> 200 0 F. However, even with required minimum reactor (continued)
SUSQUEHANNA-UNIT 1 TS / B 3.10-1 Revision 4 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B ,3.10.1 BASES BACKGROUND (continued) coolant temperatures
< 200'F, maintaining RCS temperatures within a small band during the test can be impractical.
Removal of heat addition from recirculation pump operation and reactor core decay heat is coarsely controlled by control rod drive hydraulic system flow and reactor water cleanup system non-regenerative heat exchanger operation.
Test conditions are focused on maintaining a steady state pressure, and tightly limited temperature control poses an unnecessary burden on the operator and may not be achievable in certain instances.
The hydrostatic and RCS system leakage tests requires increasing pressure to 1035 (+10, -0) psig. Tho minimum
"-csc tompcraturo aGcording to LCO 3.4.10 is approximatoly 1102F= for Unit 1. Theohyd9rotatic test proccuro deer, not oXcood the Safoat Limit cI 137-5 psig. Scram time testing required by SR 3.1.4.1 and SR 3.1.4.4 requires reactor pressures
> 800 psig.Other testing may be performed in conjunction with the allowances for inservice leak or hydrostatic tests and control rod scram time tests., APPLICABLE SAFETY ANALYSES Allowing the reactor to be considered in MODE 4 during hydrostatic or leak testig when the reactor coolant temperature is > 200 0 F, bu-t 4 212°Fduring, or as a consequence of hydrostatic or leak testing, or as a consequence of control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, effectively provides an exception to MODE 3 requirements, including OPERABILITY of primary containment and the full complement of redundant Emergency Core Cooling Systems. Since the hydrestatai er--eak-tests are performed nearly water solid, at low decay heat values, and near MODE 4 conditions, the stored energy in the reactor core will be very low. Under these conditions, the potential for failed fuel and a subsequent increase in coolant activity above the LCO 3.4.7, "RCS Specific Activity," limits are minimized.
In addition, the secondary containment will be OPERABLE, in accordance with this Special Operations LCO, and will be capable of handling any airborne radioactivity or steam leaks that could occur during the performance of hydrostatic or leak testing. The required pressure testing conditions provide adequate assurance that the consequences of a steam leak will be conservatively bounded by the consequences of the postulated main steam line break outside of primary containment (continued)
SUSQUEHANNA
-UNIT 1 TS / B 3.10-2 Revision G I PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 described in Reference
- 2. Therefore, these requirements will conservatively limit radiation releases to the environment.(continued) 1 TS / B 3.10-2 Revision O SUSQUEHANNA
-UNIT PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES APPLICABLE In the event of a large primary system leak, the reactor vessel would SAFETY ANALYSES rapidly depressurize, allowing the low pressure core cooling systems (continued) to operate. The capability of the low pressure coolant injection and core spray subsystems, as required in MODE 4 by LCO 3.5.2,"ECCS-Shutdown," would be more than adequate to keep the core flooded under this low decay heat load condition.
Small system leaks would be detected by leakage inspections before significant inventory loss occurred.For the purposes of this test, the protection provided by normally required MODE 4 applicable LCOs, in addition to the secondary containment requirements required to be met by this Special Operations LCO, will ensure acceptable consequences during normal hydrostatic test conditions and during postulated accident conditions.
As described in LCO 3.0.7, compliance with Special Operations LCOs is optional, and therefore, no criteria of the NRC Policy Statement apply. Special Operations LCOs provide flexibility to perform certain operations by appropriately modifying requirements of other LCOs. A discussion of the criteria satisfied for the other LCOs is provided in their respective Bases.LCO As described in LCO 3.0.7, compliance with this Special Operations LCO is optional.
Operation at reactor coolant temperatures
> 200'F but < 212°F can be in accordance with Table 1.1-1 for MODE 3 operation without meeting this Special Operations LCO or its ACTIONS. This option may be required due to plant conditions or P/T limits, however, which require testing at temperatures
> 200'F, while the ASME inservice test itself requires the safety/relief valves to be gagged, preventing their OPERABILITY.
Additionally, even with required minimum reactor coolant temperatures
< 200°F, RCS temperatures may drift above 200'F during the performance of inservice leak and hydrostatic testing or during subsequent control rod scram time testing, which is typically performed in conjunction with inservice leak and hydrostatic testing. While this Special Operations LCO is provided for inservice leak and hydrostatic testing, and for scram time testing initiated in conjunction with an inservice leak or hydrostatic test, parallel performance of other tests and inspections is not precluded.(continued)
SUSQUEHANNA
-UNIT 1 TS / B 3.10-3 Revision G I PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES LCO (continued)
If it is desired to perform these tests while complying with this Special Operations LCO, then the MODE 4 applicable LCOs and specified LCOs must be met. This Special Operations LCO allows changing Table 1.1-1 temperature limits for MODE 4 to "< 212" and suspending the requirements of LCO 3.4.9, "Residual Heat Removal (RHR)Shutdown Cooling System-Cold Shutdown." The additional requirements for secondary containment LCOs to be met will provide sufficient protection for operations at reactor coolant temperatures
> 200°F for the purpose of performing either-an inservice leak or hydrostatic test, and for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test-.This LCO allows primary containment to be open for frequent unobstructed access to perform inspections, and for outage activities on various systems to continue consistent with the MODE 4 applicable requirements that a;o in offoct immodiately prior to and imdiately after thiG operation4.
APPLICABILITY The MODE 4 requirements may only be modified for the performance of, or as a consequence of, inservice leak or hydrostatic tests, or as a consequence of control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, so that these operations can be considered as in MODE 4, even though the reactor coolant temperature is > 200OF. The additional requirement for secondary containment OPERABILITY according to the imposed MODE 3 requirements provides conservatism in the response of the unit to any event that may occur. Operations in all other MODES are unaffected by this LCO.ACTIONS A Note has been provided to modify the ACTIONS related to inservice leak and hydrostatic testing operation.
Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits, will not result in separate entry into the Condition.
Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.
However, the Required Actions for each requirement of the LCO not met provide appropriate compensatory measures for (continued)
SUSQUEHANNA-UNIT 1 TS / B 3.10-4 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES ACTIONS (continued) separate requirements that are not met. As such, a Note has been provided that allows separate Condition entry for each requirement of the LCO.A.1 If an LCO specified in LCO 3.10.1 is not met, the ACTIONS applicable to the stated requirements are entered immediately and complied with.Required Action A.1 has been modified by a Note that clarifies the intent of another LCO's Required Action to be in MODE 4 includes reducing the average reactor coolant temperature to < 200 0 F.A.2.1 and A.2.2 Required Action A.2.1 and Required Action A.2.2 are alternate Required Actions that can be taken instead of Required Action A. 1 to restore compliance with the normal MODE 4 requirements, and thereby exit this Special Operation LCO's Applicability.
Activities that could further increase reactor coolant temperature or pressure are suspended immediately, in accordance with Required Action A.2.1, and the reactor coolant temperature is reduced to establish normal MODE 4 requirements.
The allowed Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Required Action A.2.2 is based on engineering judgment and provides sufficient time to reduce the average reactor coolant temperature from the highest expected value to < 200'F with normal cooldown procedures.
The Completion Time is also consistent with the time provided in LCO 3.0.3 to reach MODE 4 from MODE 3.SURVEILLANCE SR 3.10.1.1 REQUIREMENTS The LCOs made applicable are required to have their Surveillances met to establish that this LCO is being met. A discussion of the applicable SRs is provided in their respective Bases.REFERENCES
- 1. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xl.2. FSAR, Section 15.6.4 SUSQUEHANNA-UNIT 1 TS / B 3.10-5 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 B 3.10 SPECIAL OPERATIONS B 3.10.1 Inservice Leak and Hydrostatic Testing Operation BASES BACKGROUND The purpose of this Special Operations LCO is to allow certain reactor coolant pressure tests to be performed in MODE 4 with temperatures as high as 212°F when operational conditions or the metallurgical characteristics of the reactor pressure vessel (RPV) require the pressure testing at temperatures
> 200°F (normally corresponding to MODE 3) or to allow completing these reactor coolant pressure tests when the initial conditions do not require temperatures
> 200°F.Furthermore, the purpose is to allow continued performance of control rod scram time testing required by SR 3.1.4.1 SR 3.1.4.1 or SR 3.1.4.4 if reactor coolant temperatures exceed 200°F when the control rod scram time testing is initiated in conjunction with an inservice leak or hydrostatic test. These control rod scram time tests would be performed in accordance with LCO 3.10.4, "Single Control Rod Withdrawal
-Cold Shutdown," during MODE 4 operation.
Inservice hydrostatic testing and system leakage pressure tests required by Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Ref. 1) are performed prior to the reactor going critical after a refueling outage.Recirculation pump operation and a water solid RPV (except for an air bubble for pressure control) are used to achieve the necessary nieeeea'ay temperatures and pressures required for these tests. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T)limits required by LCO 3.4.10, "Reactor Coolant System (RCS)Pressure and Temperature (P/T) Limits." These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated vessel neutron fluence.With increased reactor vessel fluence over time, the minimum allowable vessel temperature increases at a given pressure.
Periodic updates to the RPV P/T limit curves are performed as necessary, based upon the results of analyses of irradiated surveillance specimens removed from the vessel. Hydrostatic and leak testing may eventually be required with minimum reactor coolant temperatures
> 200 0 F. However, even with required minimum reactor coolant temperatures
< 200°F, maintaining RCS temperatures within a small band during the test can be impractical.
Removal of heat addition from recirculation pump operation and reactor core decay (continued)
SUSQUEHANNA
-UNIT 2 TS / B 3.10-1 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES BACKGROUND (continued) heat is coarsely controlled by control rod drive hydraulic system flow and reactor water cleanup system non-regenerative heat exchanger operation.
Test conditions are focused on maintaining a steady state pressure, and tightly limited temperature control poses an unnecessary burden on the operator and may not be achievable in certain instances.
The hydrostatic and RCS system leakage tests requires increasing pressure to 1035 (+10, -0) psig. Tho MiiMHUM..
vessel tomperature according toLC 3.4.10- is10-02F for Un1it 2. Th hydroetatic test p8eScUro dooc not oxcoo9d- tho- Safety Li~mit of 137-5 te.~ Scram time testing required by SR 3.1.4.1 and SR 3.1.4.4 requires rector pressures
> 800 psig.Other testing may be performed in conjunction with the allowances for inservice leak or hydrostatic tests and control rod scram time tests.APPLICABLE SAFETY ANALYSES Allowing the reactor to be considered in MODE 4 d-ring ,ydrctatirc or k.ateetsPg-when the reactor coolant temperature is > 200OF but < 212 0 F,during, or as a consequence of hydrostatic or leak testing, or as a consequence of control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, effectively provides an exception to MODE 3 requirements, including OPERABILITY of primary containment and the full complement of redundant Emergency Core Cooling Systems. Since the hydedtatiG e--leak tests are performed nearly water solid, at low decay heat values, and near MODE 4 conditions, the stored energy in the reactor core will be very low. Under these conditions, the potential for failed fuel and a subsequent increase in coolant activity above the LCO 3.4.7, "RCS Specific Activity," limits are minimized.
In addition, the secondary containment will be OPERABLE, in accordance with this Special Operations LCO, and will be capable of handling any airborne radioactivity or steam leaks that could occur during the performance of hydrostatic or leak testing. The required pressure testing conditions provide adequate assurance that the consequences of a steam leak will be conservatively bounded by the consequences of the postulated main steam line break outside of primary containment described in Reference
- 2. Therefore, these requirements will conservatively limit radiation releases to the environment.
In the event of a large primary system leak, the reactor vessel would rapidly depressurize, allowing the low pressure core cooling systems to operate. The capability of the low pressure coolant injection and core spray subsystems, as required in MODE 4 by LCO 3.5.2, (continued)
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-UNIT 2 TS / B 3.10-2 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1"ECCS-Shutdown," would be more than adequate to keep the core flooded under this low decay heat load condition.
Small system leaks would be detected by leakage inspections before significant inventory loss occurred.(continued)
SUSQUEHANNA
-UNIT 2 TS / B 3.10-2 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES APPLICABLE For the purposes of this test, the protection provided by normally SAFETY ANALYSES required MODE 4 applicable LCOs, in addition to the secondary (continued) containment requirements required to be met by this Special Operations LCO, will ensure acceptable consequences during normal hydrostatic test conditions and during postulated accident conditions.
As described in LCO 3.0.7, compliance with Special Operations LCOs is optional, and therefore, no criteria of the NRC Policy Statement apply. Special Operations LCOs provide flexibility to perform certain operations by appropriately modifying requirements of other LCOs. A discussion of the criteria satisfied for the other LCOs is provided in their respective Bases.LCO As described in LCO 3.0.7, compliance with this Special Operations LCO is optional.
Operation at reactor coolant temperatures
> 200°F but < 212°F can be in accordance with Table 1.1-1 for MODE 3 operation without meeting this Special Operations LCO or its ACTIONS. This option may be required due to plant conditions or P/T limits, however, which require testing at temperatures
> 200'F, while the ASME inservice test itself requires the safety/relief valves to be gagged, preventing their OPERABILITY.
Additionally, even with required minimum reactor coolant temperatures
< 200°F, RCS temperatures may drift above 200°F during the performance of inservice leak and hydrostatic testing or during subsequent control rod scram time testing, which is typically performed in conjunction with inservice leak and hydrostatic testing. While this Special Operations LCO is provided for inservice leak and hydrostatic testing, and for scram time testing initiated in conjunction with an inservice leak or hydrostatic test, parallel performance of other tests and inspections is not precluded.
If it is desired to perform these tests while complying with this Special Operations LCO, then the MODE 4 applicable LCOs and specified LCOs must be met. This Special Operations LCO allows changing Table 1.1-1 temperature limits for MODE 4 to "< 212" and suspending the requirements of LCO 3.4.9, "Residual Heat Removal (RHR)Shutdown Cooling System-Cold Shutdown." The additional requirements for secondary containment LCOs to be met will provide sufficient protection for operations at reactor coolant temperatures
> 200'F for the purpose of performing eihe* an inservice leak or hydrostatic test, and for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test.(continued)
SUSQUEHANNA
-UNIT 2 TS / B 3.10-3 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES LCO (continued)
This LCO allows primary containment to be open for frequent unobstructed access to perform inspections, and for outage activities on various systems to continue consistent with the MODE 4 applicable requirements that aro in offcct immodiatoly prior to and immcdatol-after this eeeratien.
APPLICABILITY The MODE 4 requirements may only be modified for the performance of, or as a consequence of inservice leak or hydrostatic tests, or as a consequence of control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, so that these operations can be considered as in MODE 4, even though the reactor coolant temperature is > 200 0 F. The additional requirement for secondary containment OPERABILITY according to the imposed MODE 3 requirements provides conservatism in the response of the unit to any event that may occur. Operations in all other MODES are unaffected by this LCO.ACTIONS A Note has been provided to modify the ACTIONS related to inservice leak and hydrostatic testing operation.
Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits, will not result in separate entry into the Condition.
Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.
However, the Required Actions for each requirement of the LCO not met provide appropriate compensatory measures for separate requirements that are not met. As such, a Note has been provided that allows separate Condition entry for each requirement of the LCO.A.1 If an LCO specified in LCO 3.10.1 is not met, the ACTIONS applicable to the stated requirements are entered immediately and complied with. Required Action A.1 has been modified by a Note that clarifies the intent of another LCO's Required Action to be in MODE 4 includes reducing the average reactor coolant temperature to < 2000F.(continued)
SUSQUEHANNA
-UNIT 2 TS / B 3.10-4 Revision 0 1 PPL Rev. 0 Inservice Leak and Hydrostatic Testing Operation B 3.10.1 BASES ACTIONS (continued)
A.2.1 and A.2.2 Required Action A.2.1 and Required Action A.2.2 are alternate Required Actions that can be taken instead of Required Action A.1 to restore compliance with the normal MODE 4 requirements, and thereby exit this Special Operation LCO's Applicability.
Activities that could further increase reactor coolant temperature or pressure are suspended immediately, in accordance with Required Action A.2.1, and the reactor coolant temperature is reduced to establish normal MODE 4 requirements.
The allowed Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Required Action A.2.2 is based on engineering judgment and provides sufficient time to reduce the average reactor coolant temperature from the highest expected value to < 200OF with normal cooldown procedures.
The Completion Time is also consistent with the time provided in LCO 3.0.3 to reach MODE 4 from MODE 3.SURVEILLANCE SR 3.10.1.1 REQUIREMENTS The LCOs made applicable are required to have their Surveillances met to establish that this LCO is being met. A discussion of the applicable SRs is provided in their respective Bases.REFERENCES
- 1. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xl.2. FSAR, Section 15.6.4 (continued)
SUSQUEHANNA
-UNIT 2 TS / B 3.10-5 Revision 0 1