Text

Proposed Amendments 254 and 219 to Licenses NPF-14 and NPF-22 Re Revised Response to GL 94-02: Long-Term Stability Solution PLA-5620
	ML031330658
Person / Time
Site:	Susquehanna
Issue date:	05/06/2003
From:	Shriver B; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GL-94-002, PLA-5620
	Download: ML031330658 (54)
	v • d • e

Bryce L. Shriver PPL Susquehanna, LLC Senior Vice President and 769 Salem Boulevard a

Chief Nuclear Officer Benvick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 blshriver@pplweb.com p

p MAY 0 6 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 254 TO LICENSE NFP-14 AND PROPOSED AMENDMENT NO. 219 TO LICENSE NFP-22:

REVISED RESPONSE TO GL 94-02:

LONG-TERM STABILITY SOLUTION PLA-5620

References:

)

Letter, V. Nerses (USNRC) to R. G. Byram (PPL), "Susquehanna Steam Electric Station Units 1 and2 (TACNOS. MA2271 and MA2445) " (Amendments 184 and 158), dated July 30, 1999.

2)

Letter, R. G. Schaaf (USNRC) to R. G. Byram (PPL), "Susquehanna Steam Electric Station, Units 1 and 2 - Issuance ofAmendment Re: Change of Implementation Date for Amendment No 184for Unit 1 andAmendment No. 158for Unit 2 (TAC Nos. MB283 7 and MB2838), "dated October 29, 2001.

3)

Letter, J. S. Post (GE) to USNRC, "Stability Reload Licensing Calculations Using Generic DI VOM Curve " (10 CFR Part 21 Report), dated August 31, 2001.

4)

PLA-4195, R. G. Byram (PPL) to USNRC, "Susquehanna Steam Electric Station Response to Generic Letter 94-02: Long Ternr Soltions and Upgrade of Interin Operating Recommendations for Thermal - Hydraulic Instabilities in Boiling Tater Reactor, " dated September 12, 1994.

Pursuant to 10 CFR 50.90, PPL Susquehanna, LLC (PPL), proposes to amend the Susquehanna Steam Electric Station Units 1 and 2 (SSES) Technical Specifications (TS).

The proposed change would delete SSES TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," and revise TS 3.4.1, "Recirculation Loops Operating."

Reference I approved changes to the SSES TS that incorporated TS 3.3.1.3 and revised TS 3.4.1 to address the Long-Term Stability Solution. Prior to implementation of these changes in the SSES TS, Reference 2 approved a change to the implementation date to November 1, 2003 to provide additional time to address the issues identified in Reference 3.

2 -

Document Control Desk PLA-5620 The Reference 3 10 CFR Part 21 report issued by General Electric (GE) on August 31, 2001 identified a non-conservative deficiency in the OPRM trip setpoint methodology. Given this deficiency, the OPRM system cannot be declared operable until a revised NRC-approved methodology providing a valid basis for the trip setpoints is available and adopted for the SSES OPRM system. On February 20, 2003 representatives of the BWROG met with NRC to discuss the progress and plans for generic resolution of the Part 21 deficiency. During this meeting, the BWROG identified plans for submittal to the NRC that would provide the basis for generic resolution in 2005. As such, implementation of the approved OPRM TS on November 1, 2003 would result in immediately declaring the OPRM system inoperable. The approved amendments would place both SSES Units in a 120-day action prior to requiring plant shutdown. The shutdown of both SSES Units would be required to remain in effect until the OPRM system could be declared operable.

The amendment proposed herein would nullify approved TS Amendments that are not yet implemented, which effectively results in no change to current SSES operation. The proposed deletion of TS 3.3.1.3 and the revision to TS 3.4.1 approved in Reference 1 would formally reinstate the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. The reinstated requirements impose interim corrective actions (ICAs) to address the potential for thermal hydraulic instability events, which were originally developed in response to Bulletin 88-07, Supplement 1. Furthermore, the PPL response to Generic Letter 94-02 (Reference 4) provided commitments that incorporated an expanded stability region and power distribution control definition to strengthen thermal hydraulic instability prevention. The resultant plant operating procedure and operator training modifications will remain in place until the design issues with the OPRM system have been resolved.

Withdrawal of the pending TS requirements for OPRM implementation will not adversely affect the continued protection of the health and safety of the public. PPL expects to resubmit a request for license amendment applicable to the final OPRM design when the design issues with the OPRM system have been resolved. This is consistent with the intent of the PPL response to Generic Letter 94-02 (Reference 4) in that PPL remains committed to supporting the industry efforts to resolve the technical issues to the satisfaction of the NRC Staff. At this time the resolution dates, and therefore resubmittal dates, remain to be determined.

The need for this change has been discussed with the SSES NRC Project Manager.

Document Control Desk PLA-5620 The proposed changes have been approved by the SSES Plant Operations Review Committee and reviewed by the Susquehanna Review Committee. In accordance with 10 CFR 50.91(b)(1), PPL is sending a copy of this letter to the Pennsylvania Department of Environmental Protection.

PPL requests approval of this change prior to October 1, 2003 (i.e., prior to the current required implementation date for the OPRM system). It is requested that the amendment implementation date be within 30 days of issuance to allow orderly implementation.

If you have any questions, please contact Mr. Michael Crowvthers at (610) 774-7766.

I declare under penalty of perjury that the foregoing is true and correct.

Sincerely, Executed on:

014 6.

oos B L.

river Sr. Vice-President and Chief Nuclear Officer

Enclosure:

PPL Evaluation of the Proposed Change Attachments:

Attachment I - Proposed Technical Specification Changes (mark-up) - Proposed Technical Specification Changes (retyped) - List of Regulatory Commitments copy: NRC Region I Mr. S. L. Hansell, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP i

ENCLOSURE to PLA-5620 PPL Evaluation REVISED RESPONSE TO GL 94-02:

LONG-TERM STABILITY SOLUTION

1.

DESCRIPTION

2.

PROPOSED CHANGE

3.

BACKGROUND

4.

TECHNICAL ANALYSIS

5.

REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria

6.

ENVIRONMENTAL CONSIDERATIONS

7.

REFERENCES

Enclosure to PLA-5620 Page 1 of 9 l

~~PPL EVALUATION

1.0 DESCRIPTION

This letter is a request to amend Operating Licenses NPF-14 and NPF-22 for PPL Susquehanna, LLC (PPL), Susquehanna Steam Electric Station Units 1 and 2 (SSES) respectively. The proposed change deletes SSES Technical Specifications (TS) 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," and revises TS 3.4.1, "Recirculation Loops Operating." These changes would reverse approved TS Amendments 184 (Unit 1) and 158 (Unit 2) (Reference 1) that are not yet implemented, which effectively results in no change to the current SSES operation. Extension of the implementation date until November 1, 2003 was approved by Amendments 196 (Unit 1) and 172 (Unit 2) (Reference 2). The implementation requirements associated with Amendments 196 (Unit 1) and 172 (Unit 2) would also be superceded with this proposed amendment.

The proposed amendment would formally reinstate the requirements currently governing operation, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events.

PPL expects to resubmit a request for license amendment applicable to the final OPRM design when the design issues with the OPRM system have been resolved. This is consistent with the intent of the PPL response to Generic Letter 94-02 (Reference 3) in that PPL remains committed to supporting the industry's efforts to resolve the technical issues to the satisfaction of the NRC Staff. At this time the resolution dates, and therefore resubmittal dates, remain to be determined.

PPL requests approval of this change prior to October 1, 2003 (i.e., prior to the current required implementation date for the OPRM system). It is requested that the amendment implementation date be within 30 days of issuance to allow orderly implementation.

2.0 PROPOSED CHANGE

The proposed change would delete SSES Technical Specifications (TS) 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation" and revise TS 3.4.1, "Recirculation Loops Operating," to remove changes previously approved in SSES Amendments 184 (Unit 1) and 158 (Unit 2) (Reference 1). Extension of the implementation date until November 1, 2003 was subsequently approved by Amendments 196 (Unit 1) and 172 (Unit 2) (Reference 2). The implementation requirements associated with Amendments 196 (Unit 1) and 172 (Unit 2) would also be superceded with this proposed amendment.

Enclosure to PLA-5620 Page 2 of 9 This change would undo these approved TS Amendments that are not yet implemented, which effectively results in no change to the current SSES operation. The proposed deletion of TS 3.3.1.3 and the revision to TS 3.4.1 would formally reinstate the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. The reinstated requirements impose interim corrective actions (ICAs) to address the potential for thermal hydraulic instability events, which were originally developed in response to Bulletin 88-07, Supplement 1. Furthermore, the PPL response to Generic Letter 94-02 (Reference 3) provided commitments that incorporated expanded stability region and power distribution control definition to strengthen thermal hydraulic instability prevention.

3.0 BACKGROUND

General Design Criterion (GDC) 10 of Appendix A to 10 CFR Part 50 requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. Additionally, GDC 12 requires that the reactor core and associated coolant, control, and protection systems be designed to assure that power oscillations which can result in conditions exceeding acceptable fuel design limits are either not possible, or can be reliably and readily detected and suppressed.

Under certain conditions, boiling water reactor cores may exhibit thermal hydraulic instabilities. These instabilities are characterized by periodic power and flow oscillations. If the oscillations become large enough, the fuel cladding integrity minimum critical power ratio (MCPR) safety limit and GDC 10 and 12 requirements may be challenged. Based on this possibility, SSES is currently operating with certain interim corrective actions (ICAs) to address the potential for thermal hydraulic instability events, which were originally developed in response to Bulletin 88-07, Supplement 1.

Furthermore, the PPL response to Generic Letter 94-02 (Reference 3) provided commitments that incorporated expanded stability region and power distribution control definition to strengthen thermal hydraulic instability prevention. The plant operating procedures and operator training pursuant to implementation of the ICAs will continue to remain in place until the OPRM system is declared OPERABLE.

These requirements limit the probability of an instability event by restricting the duration of any entry into the regions of the power to flow map most susceptible to instability under anticipated entry conditions. Operator actions are also required by the ICAs when conditions consistent with the onset of thermal hydraulic oscillations are observed. These actions result in the suppression of conditions required for an instability event and thereby prevent any potential challenge to the MCPR safety limit.

Enclosure to PLA-5620 Page 3 of 9 As committed to in response to GL 94-02 (Reference 3), an OPRM system was installed at SSES consistent with the Asea Brown Boveri Combustion Engineering (ABB-CE)

Option III long-term solution for the thermal hydraulic instability issue. The intent of this OPRM system is to provide an RPS trip function to provide automatic detection and suppression of conditions that might result in a thermal hydraulic instability event and provide elimination of the manual ICAs. Implementation of SSES Amendments 184 (Unit 1) and 158 (Unit 2) requires that the OPRM system, including RPS trip function, be fully operable. Additionally implementation eliminates the ICAs from the Technical Specifications.

SSES TS Amendments 184 (Unit 1) and 158 (Unit 2) were issued by the NRC on October 29, 2001 (Reference 1). Extension of the implementation date until November 1, 2003 was subsequently approved as Amendments 196 (Unit 1) and 172 (Unit 2) (Reference 2). This deferral was based on a OCFR Part 21 report issued by General Electric (GE) on August 31, 2001 (Reference 4), which identified a non-conservative deficiency in the OPRM trip setpoint methodology. The OPRM system can not be declared operable until a revised NRC-approved methodology providing a valid basis for the trip setpoints is available and adopted for the SSES OPRM system.

From August 2001 through February 2003 the BWROG has performed analyses and has met with the NRC to review resolution status and plans. On February 20, 2003 representatives of the BWROG met with the NRC to discuss the progress and plans for generic resolution of the OPRM system design issue. During this meeting the BWROG representatives identified plans for submittal to the NRC that would provide the basis for generic resolution in 2005.

Precedent for the amendment proposed by PPL is found in the withdrawal and NRC acceptance of OPRM TS submittals by a number of utilities (refer to References 5, 6, 7, 8, and 9). NRC acceptance of the OPRM TS withdrawal by these utilities approved continued operation of these facilities with ICAs similar to those currently implemented for SSES. In these cases the amendment request withdrawal was made prior to NRC issuance of an approved amendment. The situation for SSES is different. At SSES the "withdrawal" necessitates an amendment request since Amendments 196 (Unit 1) and 172 (Unit 2) have been issued.

4.0 TECHNICAL ANALYSIS

There are no safety consequences as a result of this change. The amendment proposed herein would undo approved TS Amendments 196 (Unit 1) and 172 (Unit 2) that are not yet implemented, which effectively results in no change to the current SSES operation.

Implementation of SSES Amendments 196 (Unit 1) and 172 (Unit 2) requires that the OPRM system, including RPS trip function, be fully operable.

Enclosure to PLA-5620 Page 4 of 9 The proposed change to delete TS 3.3.1.3 and revise TS 3.4.1 would formally reinstate the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. The reinstated requirements impose interim corrective actions (ICAs) to address the potential for thermal hydraulic instability events, which were originally developed in response to Bulletin 88-07, Supplement 1. Furthermore, the PPL response to Generic Letter 94-02 (Reference 4) provided commitments that incorporated expanded stability region and power distribution control definition to strengthen thermal hydraulic instability prevention.

NRC granted deferred implementation of the OPRM TS until November 1, 2003 in SSES Amendments 196 (Unit 1) and 172 (Unit 2) (Reference 2). In this evaluation, the NRC noted that the existing ICAs "are intended to insure that the plant is not operated under combinations of thermal power and core flow that are conducive to thermal-hydraulic instability." The evaluation concluded that these ICAs will "provide adequate core protection." The deferral was based on a 10 CFR Part 21 report issued by GE on August 31, 2001 (Reference 5), vhich identified a deficiency in the OPRM trip setpoint methodology. As stated in the NRC safety evaluation approving this deferral (Reference 2):

"The NRC Staff expects that the deficiency can be resolved on a generic basis, and that the staff would review any proposed resolution before implementation at any specific facility."

At this time, the generic resolution is not yet resolved. On February 20, 2003 representatives of the Boiling Water Reactor Owner's Group (BWROG) Detect and Suppress Methodology subcommittee met with the NRC to discuss the progress and plans for generic resolution of the OPRM system design issue. During this meeting the BWROG representatives identified plans for submittal to the NRC that would provide the basis for generic resolution in 2005. Final resolution date and, therefore, formal resubmittal of the OPRM TS, remains to be determined.

This proposed amendment is needed because the OPRM set-point specified in the LCO 3.3.1.3 does not provide adequate Minimum Critical Power Ratio (MCPR) safety limit protection for anticipated reactor instability events (as identified in the 10 CFR 21 Report).

The OPRM system can not be declared operable until a revised methodology that provides a valid and safe basis for the trip setpoints is adopted. If this proposed amendment is not approved prior to November 1, 2003, both of the SSES Unit 1 and Unit 2 OPRM systems will have to be declared inoperable. The resulting actions would place both SSES Units in a 120-day limitation prior to requiring plant shutdown actions.

This shutdown of both SSES Units would be required to remain in effect until the OPRM system could be declared OPERABLE.

Enclosure to PLA-5620 Page 5 of 9 In summary, the TS changes granted by SSES Amendments 196 and 172 cannot be implemented and need to be replaced with the changes proposed herein to continue the safe operation of SSES Units I and 2. The changes proposed herein define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. Approval of this proposed change is appropriate based on:

(1)

The stated NRC position to resolve the issue generically prior to imposing implementation; (2)

The acceptability of continuing operation with the ICAs; and (3)

The nature of and extended resolution plan for the unresolved setpoint issue.

In conclusion: (1) there is reasonable assurance that the health and safety of the public wvill not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The proposed amendment revises Susquehanna Steam Electric Station Units 1 and 2 (SSES) Technical Specifications (TS). The change deletes SSES Technical Specifications (TS) 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation" and revises TS 3.4.1, "Recirculation Loops Operating" to remove changes previously approved in Amendments 184 and 158 for SSES Units 1 and 2 respectively and required to be implemented by November 1, 2003 by Amendments 196 and 172. The revised TS 3.4.1 would formally reinstate the SSES TS requirements that have been in effect since November 1989 (Amendments 93 and 60) and are currently governing operation.

PPL Susquehanna, LLC (PPL) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

Enclosure to PLA-5620 Page 6 of 9

1.

Does the proposed change involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated?

Response: No.

The OPRM system is not an initiator to any accident sequence analyzed in the Final Safety Analysis Report (FSAR). The changes do not involve a physical change to structures, systems, or components (SSCs) since the RPS trip function has not been installed and does not alter the method of operation or control of SSCs since the OPRM system has not be declared OPERABLE. The current assumptions in the safety analysis regarding accident initiators and mitigation of accidents (including assumed protection of fuel design limits) are unaffected by these changes. No additional failure modes or mechanisms are being introduced and the likelihood of previously analyzed failures remains unchanged.

Operation in accordance with the proposed Technical Specification (TS) ensures that the protection from thermal hydraulic instabilities remains as previously evaluated and the protection for fuel design limits remain as described in the FSAR. Therefore, the mitigative functions will continue to provide the protection assumed by the existing analysis.

Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change does not involve a physical alteration of the plant. No new equipment is being introduced, and installed equipment is not being operated in a new or different manner. There are no setpoints affected by this change at which protective or mitigative actions are initiated. This change will not alter the manner in which equipment operation is initiated, nor will the functional demands on credited equipment be changed. No alterations in the procedures that ensure the plant remains within analyzed limits are being proposed, and no changes are being made to the procedures relied upon to respond to an off-normal event as described in the FSAR. As such, no new failure modes are being introduced. The change does not alter assumptions made in the safety analysis and licensing basis.

Enclosure to PLA-5620 Page 7 of 9

3.

Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The margin of safety is established through equipment design, operating parameters, and the setpoints at which automatic actions are initiated. The proposed change is acceptable because the required protection from thermal hydraulic instabilities remains as previously evaluated and the protection for fuel design limits remain as described in the FSAR. Operation in accordance with the proposed TS ensures that the margin of safety is maintained. Therefore, the change does not involve a significant reduction in a margin of safety.

5.2 Applicable Regulatory Requirements/Criteria General Design Criterion (GDC) 10 of Appendix A to 10 CFR Part 50 requires that the reactor core and associated coolant, control, and protections systems be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. Additionally, GDC 12 requires that the reactor core and associated coolant, control, and protection systems be designed to assure that power oscillations which can result in conditions exceeding acceptable fuel design limits are either not possible, or can be reliably and readily detected and suppressed.

Under certain conditions, boiling water reactor (BWR) cores may exhibit thermal hydraulic instabilities. These instabilities are characterized by periodic power and flow oscillations. If the oscillations become large enough, the fuel cladding integrity minimum critical power ratio (MCPR) safety limit and GDC 10 and 12 requirements may be challenged. Based on this possibility, SSES is currently operating with certain interim corrective actions (ICAs) to address the potential for thermal hydraulic instability events, which were originally developed in response to Bulletin 88-07, Supplement 1.

Generic Letter 94-02, "Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors,"

required further efforts for long term corrective actions. The PPL response to Generic Letter 94-02 (Reference 3) provided commitments that incorporated expanded stability region and power distribution control definition to strengthen thermal hydraulic instability prevention. When the design issues with the OPRM system have been resolved, supporting the ability of the OPRM system to perform its intended function, PPL will resubmit a request for license amendment applicable to the final OPRM design.

This is consistent with the intent of the PPL response to Generic Letter 94-02 (Reference 3) in that PPL remains committed to supporting the industry efforts to resolve the technical issues to the satisfaction of the NRC Staff.

Enclosure to PLA-5620 Page 8 of 9 SSES FSAR Sections 3.1 and 3.13 provide detailed discussion of SSES compliance with the applicable regulatory requirements and guidance, which is not impacted by this amendment. SSES FSAR Section 4.4.4.6 discusses the thermal-hydraulic stability analysis. For reload cores, a confirmatory analysis is performed to demonstrate the continued applicability of the core stability regions, which assure that the ICAs remain valid for each cycle. The analysis is based on comparison of core stability performance (i.e., variations in decay ratio for operating conditions at representative state points near the stability exclusion region) to previously analyzed cycles.

6.0 ENVIRONMENTAL CONSIDERATION

S 10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions, which are eligible for categorical exclusion from the requirement to perform an environmental assessment.

A proposed amendment to an operating license for a facility does not require an environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (3) result in a significant increase in individual or cumulative occupational radiation exposure. PPL Susquehanna, LLC has evaluated the proposed change and has determined that the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Accordingly, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with issuance of the amendment. The basis for this determination, using the above criteria, follows:

Basis As demonstrated in the No Significant Hazards Consideration Evaluation, the proposed amendment does not involve a significant hazards consideration.

There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be installed) or change in methods governing normal plant operation.

There is no significant increase in individual or cumulative occupational radiation exposure. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be installed) or change in methods governing normal plant operation.

Enclosure to PLA-5620 Page 9 of 9

7.0 REFERENCES

1.

Letter, V. Nerses (USNRC) to R. G. Byram (PPL), "Susquehanna Steam Electric Station, Units I and 2 (TAC Nos. MA2271 and MA2445)" (Issuance of Amendments 184 [Unit 1] and 158 [Unit 2]), dated July 30, 1999.

2.

Letter, R. G. Schaaf (USNRC) to R. G. Byram (PPL), "Susquehanna Steam Electric Station, Units and 2 - Issuance of Amendment RE: Change of Implementation Date for Amendment No. 184 for Unit 1 and Amendment No. 158 for Unit 2 (TAC Nos. MB2837 and MB283 8)" (Issuance of Amendments 196 [Unit 1] and 172 [Unit 2]), dated October 29, 2001.

3.

PLA-4195, R. G. Byram (PPL) to USNRC, "Susquehanna Steam Electric Station Response to Generic Letter 94-02: Long Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors," dated September 12, 1994.

4.

Letter, J. S. Post (GE) to USNRC, "Stability Reload Licensing Calculations Using Generic DIVOM Curve" (10 CFR Part 21 Report), dated August 31, 2001.

5.

Letter, USNRC to 0. D. Kingsley, "Clinton Power Station Withdrawal of Amendment Request (TAC MB2133)," dated September 18, 2001.

6.

Letter, USNRC to 0. D. Kingsley, "Limerick Generating Station, Units 1 and 2 -

Withdrawal of Amendment Request RE: Oscillation Power Range Monitor Reactor Scram Function (TAC NOS. MB2194 and MB2195)," dated January 28, 2002.

7.

Letter, USNRC to H. W. Keiser, "Hope Creek Generating Station, Withdrawal of An Amendment Request, Oscillation Power Range Monitor (TAC No. MB0589)."

dated November 28, 2001.

8.

Letter, USNRC to 0. D. Kingsley, "LaSalle County Station, Units 1 and 2 -

Withdrawal of an Amendment Request (TAC Nos. MB0473 and MB0474),"

dated October 4, 2001.

9.

Letter, USNRC to 0. D. Kingsley, "Peach Bottom Atomic Power Station, Units 2 and 3 - Withdrawal of Amendment Request RE: Oscillation Power Range Monitor Reactor Scram Function (TAC Nos. MB1 165 and MB1 166)," dated January 10, 2002.

to PLA-5620 Proposed Technical Specification Changes (Markups)

(Units 1 & 2)

--W

NOTE:

The LCO 3.4.1 inserts provided are the SSES TS Amendment 178 and 151 pages. The markups are editorial, to make the pages consistent between Unit 1 and Unit 2, and to correct format deficiencies.

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)

USE AND APPLICATION....................

Definitions Def nit ons Logical Connectors..............

Completion Times....................

Frequency..........

SAFETY LIMITS (SLs)

SLs SL Violations.....................

LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.

SURVEILLANCE REQUIREMENT (SR) APPLICABILITY........

1.1-1 1.1-1 1.2-1 1.3-1 1.4.1 2.0-.1 2.0-1 2.0-1 3.0-1 3.0-4 REACTIVITY CONTROL SYSTEMS...............

3.1-1 Shutdown Margin (SDM) 3.1-1 Reactivity Anomalies................

3.1-5 Control Rod OPERABILITY..............

3.1-7.

Control Rod Scram Times 3.1-12 Control Rod Scram Accumulators...........

3.1-15 Rod Pattern Control 3.1-18 Standby Liquid Control (SLC) System.3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves 3.1-25 POWER DISTRIBUTION LIMITS...............

3.2-1 Average Planar Linear Heat Generation Rate (APLHGR) 3.2-1 Minimum Critical Power Ratio (MCPR) 3.2-3 Linear Heat Generation Rate (LHGR) 3.2-5 Average Power Range Monitor (APRM) Gain and Setpoints 3.2-7 INSTRUMENTATION Reactor Protection System (RPS) Instrumentation Source Range Monitor (SRM) Instrumentation...

Oscil ltion Pwer faingo Mnitoring (OPRM) 3.3-1 3.3-1 3.3-10 fT3b usrtalmtl iiI vQ Control Rod Block Instrumentation 3.3-16 Feedwater - Main Turbine High Water Level Trip Instrumentation...............

3.3-21 Post Accident Monitoring (PAM) Instrumentation...

3.3-23 Remote Shutdown System...............

3.3-26 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation.................

3.3-29 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation 3.3-33 Emergency Core Cooling System (ECCS) Instrumentation 3.3-36 Reactor Core Isolation Cooling (RCIC) System Instrumentation.................

3.3-48 Primary Containment Isolation Instrumentation 3.3-52 Secondary Containment Isolation Instrumentation 3.3-63 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation 3.3-67 SUSQUEHANNA - UNIT 1 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.3 3.3.1.1 3.3.1.2 3.2.1 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.4.2 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.7.1 I

i Amendment No. 184

OPRM Instrumentati 3.3.3

\\ 2 W

</67 3.3 INS UMENTATION 3.3.1.3 Os llation Power Range Monitor (OPRM) Instrumentation LCO 3.3.1.3 Four channels of the OPRM instrumentation shall/e OPERABLE.

Each OPRM channel Period Based Algorithm (Sp) lowable Value shall be less than or equal to 1.09 at confirmation unt permissive (Np) of 10.

APPLICABILITY:

Th mal Power 2 25% RTP.

ACTIONS:

NOTE------------------ -----------------------

Separate Condition entry\\is allowed for each channe CONDITION A. One or more required channels inoperable.

/

B. OPRM tril not mainl

/

C. Requi/ed Action and assdiated Completion Ti not met.

/

REQUIRED AC ON Place ch/nel in trip.

k associated RPS

) system in trip.

tiate alternate d to detect and

)h ss thermal

,a c instability illa<ions.

/

B.1 AND B.2 Initiate a rnate I

method to de ct and suppress ther 1 hydraullic inst ility oscillations.

Restore OPRM trip\\

capability

-4 1

C. 1 Reduce THERMAL POWER

< 25% RTP.

COMPLETION TIME 30 days 30 days 30 days 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 120 days

\\

4 h rs n

I _________________________

SU UEHANNA - UNIT 1 I

Anendme; fo. 184 l

TS / 3.3-15a

OPRM Instrumenta on

\\ A

<REMO1JE

~~~P 3 /

SUR EILLANCE REQUIREMENTS N----------------------------NOTE----------------------

When a hannel is placed in an inoperable status solely for perf irmance of required urveillances. entry into associated Conditions and R uired Actios may be de yed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the OPRM System mai ains trip capability.

X - -

SURVEILLANCE SR 3.

ays SR 3.3.1.3.2 Calibra the local power ra e monitors.

1000 MWD/MT average core exposure SR 3.3.1.3.3 Neutron detectors a excluded.

Perform CHANNE AL TION.

24 months SR 3.3.1.3.4 Perform L C SYSTEM FUNC NAL-TEST

-24 months SR 3.3.1.3.5 Veri OPRM is not bypassed whe THERMAL 24 months POW is > 30% RTP and core flow 60 M

Hr.

SR 3.3.1.3.-

NOTE-------------------\\

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within 24 nths on a limits.

STAG RED TEST BASIS I

SQUEHANNA - UNIT 1 Amendment

' 1 84 TS / 3.3-15b

Recirculation Loops Operating 3.4.1 3.4 REACT COOLANT SYSTEM (RCS) 3.4.1 Rcirculation Loops Operati g LCO

.4.1 Two recircul ion loops with matched lows shall be in operation.

OR One r irculation loop may be n operation provided the foll ing limits are applie when the associated LCO is app icable:

LCO 3.2.1, "AVERAG PLANAR LINEAR HEAT GENERATIO TE (APLHGR)," single oop operation limits specifi in the COLR:'

b. LCO 3.2.2. "M IMUM CRITICAL POWER RATIO (M R)." single loop operati n limits specified in the COL

c.

LCO 3.2.3 "LINEAR HEAT GENERATION RATE LHGR)," single loop ope tion limits specified in the OLR. and

d. LCO 3..1.1. "Reactor Protection Sys em (RPS)

Instr mentation," Function 2.b CAy age Power Range Monjors Flow Biased Simulated Th Imal Power-High).

Al owable Value of Table 3.3.1.1 is reset for single 1 op operation.

e.

ecirculation pump speed is 80%.

Note---

-Note-~~~~~~~cicltinlo p-i Required limit an setpoint resets for single ecirculation loop operation y be delayed for u to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transiti from two recirculation loo operation to s gle recirculation loop oper ion.

APPLICABILITi MODES 1 and 2.//

KtT X IT 1I A

£L'4oflIT -I k

Amendment No.

1-78, 1,

TS / 3.4-1 SUSQUEHANNA - UNIT 1

Reci rcu I ati on Loops Operati ng 3 4.1 Amnendment No. 478, 1E I

I SUSQUEHANNA - UNIT TS 3.4-2

I I

AmendmentNo.

78, 181 TS / 3.4-3-.

SUSQUEHANNA - UNIT

Recirculation Loops Operating 3.4.1

/

SURVEILLANCE IZQUIREMENTS

/

SURVEILL -CE

/ J FREQUENCY 3.1.1

------ NOTE------------ -----

Not requir to be performed until/4 hours.

after bot recirculation loops ar in operati.

Verfy recirculation loop t pump flow m match with both recir ation loops in peration is:

a. < 10 million lb hr when operating at

< 75 million

/hr total core flow; and

b. < 5 milli lbm/hr when operating 75 mil on lbm/hr total core f

NOTE--------

Only re ired to be met during ingle loop opera ons.

V ify recirculation pump speed is within e limit specified in e LCO.

I R 3.4.1.2 4-24 hour

/~~~~/

24 us mendment No.

78, 0e.

1_1_~ ~~ ~

SR I

I

_11 I

4, TS / 3.4-4 SUSQUEHANNA - UNIT 1 rl-

Recirculation Loops Operating 3.4.1 UAmendment No. P78>. 184 TS / -3.4 SUSQUEHANNA - UNIT I

1MvSERT 1

(Uotr /)

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1

- Two recirculation loops with matched flows shall be in.

operation with a THERMAL POWER/cor 4low condition outside of Regions I and II of Figure 3.44.

OR One recirculation loop may be inoperation provided the following limits are applied when the associated LCO is a able wI a THERMAL POWER/

flow condition outside (of Regions I and II of Fi ur 3

a. LCO 3.2.1.

(APLHGR)."

COLR; "AVERAGE PLANAR LINEAR HEAT GENERATION RATE single loop operation limits specified in the

b. LCO 3.2-.2. "MINIMUM CRITICAL POWER RATIO (MCPR)." single loop operation limits specified in the COLR;

c. LCO 3.2.3. "LINEAR HEAT GENERATION loop operation limits specified in RATE (LHGR)." single the COLR; G

d. LCO 3.3.1.1. -"Reactor Protection System (RPS)

Instrumentation." Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High),

Allowable Value of Table 3.3.1.1-1 is reset for single loop operatio

e.

Recirculation pump speed is 80%.

Note---------------------------------

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY:

MODES 1 and 2.

SUSQUEHANNA - UNIT 1 3.4-1 kmendment 178

(UA

)CT_i)

(tn1l

)

Z-Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Total core flow as a A.1

.Place reactor mode Immediately function of THERMAL switch in the POWER within Region I shutdown position.

of Figure 3.4.1-1.

OR No recirculation loops operating while in MODE 1d3 B. --------NOTE----------

B.1 Place the reactor Immediately Only applicable when mode switch in the in Region II of shutdown position.

Figure 3.4.1-1C Two or more APRM readings oscillating with one or more oscillating 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating.and deactivating with a period > 1 second and

< 5 seconds, OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period > 1 second and < 5 seconds.

OR (continued)

SUSQUEHANNA - UNIT 1 3.4-2 kmendment 178

jAJaeRT

-3 (L(nIr Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

Less than 50% of required LPRM upscale alarms OPERABLE 0 C. Total core flow as a C.1 Initiate action to Immediately function of THERMAL restore total core POWER within Region II flow as a function of Figure 3.4.1-1.

of THERMAL POWER outside of Region II.

D. Recirculation loop D.1 Declare the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months flow mismatch not recirculation loop within limits.

with lower flow to be "not in operation.."

E. No recirculation loops E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in operation while in MODE 2 OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA - UNIT 1 3.4 kmendment 178

Recirculation VCRT

.( un!r, I.

Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS._._.

SURVEILLANCE FREQUENCY SR 3.4.1.1

NOTE--------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation oops in operation.is:

a. s 10 million lbm/hr when operating at

< 75 million lbm/hr total core flow:

and

b. s 5 million.lbm/hr when operating at 2 75 million bm/hr total core flow.

SR. 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER is outside of Region I and II of Figure 3.4.1-1.

SR 3.4.1.3

NOTE-------------------

Only required to be met during single loop operations.

Verify recirculation pump speed is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the limit specified in the LCO.

SUSQUEHANNA - UNIT 1 Amendment 178 3.4-4

I/AJ%9Rr (Un/TaL)

Recirculation Loops Operating 3.4.1 7........

00 10 B O REGION 7....

I.......

7 3.5 40 45 50 55 Core Flow (Million lbm/hr) 80 8I 70 Figure 3.4.1-1 Thermal Power Stability Restrictions SUSQUEHANNA - UNIT 1I.-

mnmn 7

100 910 80.

LUJ dI-a-

0 E

-a 0

X-CD 0

U-70 -

80-50 -

40-307-20 -

10 -

30 I

3.4-5 0

Arnendment 178

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)

I 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 3.2

.3.2.1 3.2.2 3.2.3 3..2.4 USE AND APPLICATION.................

Definitions Logical Connectors.

Logial onnctos...............

.Completion Times.

Frequency SAFETY LIMITS (SLs)

SLs SL Violations LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY...

SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.

REACTIVITY CONTROL SYSTEMS..............

Shutdown Margin (SDM)

Reactivity Anomalies...............

Control Rod OPERABILITY Control Rod Scram Times Control Rod Scram Accumulators...........

Rod Pattern Control Standby Liquid Control (SLC) System.......

Scram Discharge Volume (SDV)

Vent and Drain Valves 1.1-1

i 1.1-1 1.2-1 1.3-1 1.4-1

2.0-1 2.0-1 2.0-1 3.0-1 3.0-4

3.1-1 3.1-1

3.1-5 3.1-7 3.1-12 3.1-15 3.1-18 3.1-20 3.1-25 POWER DISTRIBUTION LIMITS...............

3.2-1 Average Planar Linear Heat Generation Rate (APLHGR) 3.2-1 Minimum Critical Power Ratio (MCPR) 3.2-3 Linear Heat Generation Rate (LHGR) 3.2-5 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 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation.

.3.3-10

-3.3.1.3

-OzcillDtibn Po'cr Range Monitor (OPrDT)

ZT4J WE l e

~~~.

... v.

.o 3.3.2.1 Control Rod Block Instrumentation.........

3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation.................

3.3-20 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation...

3.3-22 3.3.3.2 Remote Shutdown System...........

3.3-26 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation..

3.3-29 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation 3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation.

3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation 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 Amendment No.

E I

SUSQUEHANNA - UNIT 2 i

OPRM Instrumenta on

3..1.3

3.

\\

INSTRUMENTATION 3.3. 3 Oscillation Power Range Monitor (OPRM) Instrumentati LCO 3..1.3 Four channels of the OPRM instrumentation all be OPERABLE.

Each OPRM channel Period Based Algorithm p) Allowable Value shall be less than or equal to 1.1 at a confirmation count permissive (Np) of 10.

APPLICABILIT Thermal Power 2 25% RTP.

ACTIONS:

NOTE---------------------------------------

Separate Conditio entry is allowed for each chann CONDITION REQUIRED AC ON COMPLETION TIME A. One or more require A.1 Place ch nel in trip.

30 days channels inoperable\\O/

2 Plac associated RPS tri system in trip.

30 days A.3 Initiate alternate thod to detect and 30 days

/

spress thermal hyaulic instability osci lations.

B. OPRM trip capability B.1 Initiate alternate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months not maintained.

method to etect and suppress thrmal hydraullic i tability oscillations.

AND B.2 Restore OPRM trip 120 days capability C. Required ction and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associad Completion

< 25% RTP.

Time NN t met. 2 SUSQ ANA - UNIT 2 TS / 3.3-15a A

eto18

OPRM Instr entation R416Vz 10-Ci >

-/>3.3.1.3 SURe ILLANCE REQUIREMENTS NOTE--------------------/

When a hannel is placed in an inoperable status solely for p rformance of required Surveillances, entry into associated Conditions an Required Actions may be de yed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the OPRM System intains trip

.capability\\

SURVEILLANCE FREQUENCY SR 3.3.1.3.1 Pe orm CHANNEL FUNCTIONAL TEST 184 days SR 3.3.1.3.2 Calibrae the local power ange monitors.

1000 MWD/MT average core

exposure, SR 3.3.1.3.3 TE-

-Neutron detector re excluded.

Perform CHANNEL CAL RATION.

24 months SR 3.3.1.3.4 Perform LO C SYSTEM FUN XONAL TEST

-24 months SR 3.3.1.3.5 Verify PRM is not bypassed wh THERMAL

24 months POWER is 2 30% RTP and core flo C 60 MLb/ r-SR 3.3.1.3.6

NOTE--------------

Neutron detectors are excluded.

'Verify the RPS RESPONSE TIME is within 24 months.on a limits.

TAGGERED TEST

/~~~~~~~~~~~~~~

-BSIS I SUHANNA - UNIT 2 AmX6nt No. 158 TS / 3.3-15b

Recirculation Loops Operating 3.4.1 3.4 REACTOR COO N SYSTEM (RCS) 3.4.1 Recirc ation Loops Operating LCO 3.4 Two recirculation loops-h matched flows shall be in operation.

OR One recirculatio loop may be in operation provid the following limi are applied when the associate LCO is applicable:

a. LCO J.2.1 "AVERAGE PLANAR LINEAR HEA GENERATION RATE (CLHGR)," single loop operation 11 ts specified in the XLR:;

LCO 3.2.2. "MINIMUM CRITICAL P ER RATIO (MCPR)." single loop operation limits speci d in the COLR:

c. LCO 3.2.3. "LINEAR HEAT ERATION RATE (LHGR)." single loop operation limits secified in the COLR, and

d. LCO 3.3.1.1. "React Protection System (RPS)

Instrumentation."

nction 2.b (Average Power Range Monitors Flow Bi ed Simulated Thermal Power-Hig Allowable Value f Table 3.3.1.1-1 is reset for ngle loop operation

e. Recirculati pump speed is < 80%

Note----------------- -

Required limit and setpoint esets for single recirculation oop operation may be delayed for up to 12 ho s after transition from two r irculation loop operation to single recir ulation loop operation.

APPLICABILITY:

MOD 1 and 2.

/

/IvsetzT

('AnIr 2 AmendmentNo. 454, 158 TS 3.4 SUSQUEHdANNA - UNIT 2

Recirculation Loops Operating 3.4.1 CO 1'TION REQUIRED AC 2' I

COMPLETION TIME A.

recirculation loops operating while in MODE 1 B. Recirculation loop flow mismatch not within limits.

/

Z C. No r rculation loops in peration while in E2 OR Single Recirculation I nn rniirgd limit.C and setpoints not established within required time.

A.1 B.1I C.1 P1

.reactor.mode itch in the shutdown position.

Declare the recirculation loop with lower flow to be "not in operation."

Be in MOD

..Immediately 4-2 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months L

I ________________________

,7 SUSQUEHANNA - UNIT 2 ACTIONS 0.

K

/11",

A I

It

--1/

I Ame'ndment No.

51, TS / 3.4-2 1

5 is~~~~~~~

1

/ /UEg

.v (n-I-)I

( /AJ7

.3 Anendment No. 151, 15 TS / 3.4-3-.

SUSQUEHANNA - UNIT 2

.Reci rcul ati on Loops Operating 3.4.1 A

§URVEILLANCE R2i UIREMENTS

/'

SURVEILLANCE/

SR

.4.1.1

--- NOTE-------------------

Not required o be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both ecirculation loops are in

/

~~operatiow

/

~~~~--

Ve fy recirculation loop jet pum ow smatch with both recirculation oops in operation is:

a. < 10 million lbm/hr e operating at

< 75 million bm/h total core flow:

and

b. < 5 million i /hr when operating at 75 milP n lbm/hr total core flow.

/

v~~~~~~~~~~~~~~~~~

FRE C

z 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.4.1.2 -----------

NOTE-----------------

Only equired to be met during single op ope ations.

/

Verify recirculation pump spe is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the limits specified in the CO.

/

Amendment No. 451, 1

K p-(kV' r 2)\\

.TS / 3.4-4 SUSQUEHANNA - UNIT 2

Recirculation Loops Operating 3.4.1 FT BLANK

)

.. /A.

X v s Amendment No.

54, 151

- TS / 3.4-5:

SUSQUEHANNA - UNIT 2

AJS6EAT- /

(an IT 2.)

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with a THERMAL POWER/core flow condition outside of Regions I and II of Figure 3.4.1-1.

OR One recirculation loop may be in operation with a THERMAL

,POWER/core flow condition outside of Regions I and II of Figure 3.4.1-1 provided the following limits are applied when the associated LCO is applicable:

a. LCO 3.2.1.

(APLHGR)."

COLR; "AVERAGE PLANAR LINEAR HEAT GENERATION RATE single loop operation limits specified in the

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)." single.

loop operation limits specified in the COLR:

c. LCO 3.2.3. "LINEAR HEAT GENERATION loop operation limits specified in RATE (LHGR)." single the COLR; (2

d. LCO 3.3.1.1. "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High).

Allowable Value of Table 3.3.1.1-1 is reset for single loop operation

e. Recirculation pump speed is s 80%0 Note---------------------------------

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY:

MODES 1 and 2.

SUSQUEHANNA - UNIT 2 Amendment 151 3.4-1

':( Un7 Zr.2) -.2.

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Total core flow as a A.1 Place reactor mode Immediately function of THERMAL switch in the POWER within Region I shutdown position.

of Figure 3.4.1-1.

OR No recirculation loops operating while in MODE I.

B. -NOTE-B.1 Place the reactor Immediately Only applicable when mode switch in the in Region II of shutdown position.

Figure 3.4.1-l4-.

Two or more APRM readings oscillating with one or more oscillating 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating and deactivating with a period > 1 second and 5 seconds, OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period > 1 second and < 5 seconds.

OR (continued)

SUSQUEHANNA - UNIT 2 3.4-2 Amendment 151

3 (an7 m)

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

Less than 50% of required LPRM upscale alarms OPERABLEE.

C. Total core flow as a C.1 Initiate action to Immediately function of THERMAL restore total core POWER within Region II flow as a function' of Figure 3.4.1-1.

of THERMAL POWER outside of Region D. Recirculation loop D.1 Declare the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months flow mismatch not recirculation loop within limits.

with lower flow to be "not in-operation'."

E. No recirculation loops E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in operation while in MODE 2D OR Single Recirculation Loop required limits and setpoints not established wi thi n required time.

SUSQUEHANNA - UNIT 2 3.4-3 Amendment 151

j,str L/

(Un'r-a Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 --------------

NOTE--- --------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a. < 10 million bm/hr when operating at

< 75 million bm/hr total core flow; and

b.

5 million bm/hr when operating at

> 75 million bm/hr total core flow.

SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER is outside of Region I and II of Figure 3.4.1-1.

SR 3.4.1.3

NOTE-------------------

Only required to be met during single loop operations.

Verify recirculation pump speed is-within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the limits specified in the LCO.

SUSQUEHANNA - UNIT 2

Amendment 151 3.4-4

ti nt-rz)

Recirculation Loops -Operating 3.4.1 P1 100

.. ~~~~~~~~~~~~~~~~.

......... I..... I..... I....',','..'

0 -

D?'

DV............

H~~~~~~~~~~~~~~~~~~~.

u 0

0 40 1

_ ~~~~~~~~~~~~~~~~~......................

Q 30 ~~~~~~~~~~~~~~~~~~~~~~.

s o

~~~~~~~~~~~~~...

, ~~~~~~~~~~~~..............

~~~~~~~~...........

~~~~~~~~~.................................

70~~

~~~~~~~~~~~~~.

O- ~~~~~~~~~~~~~~.

30~~~~~~~~~~~~~~~~~~~~0 40 45 50...5.........

Fi~~~~~~~~~~~~~~~~~~.............

4.1-t........

i...

o 50 30 35 40 5-0 55endme0 15 7 Core Flow (Mtllion~~.... lbm/hr)....

Figure 3

4 11~ ~~~~~~..............

Thermal Power Stability Restrictions.................

p~

~ ~~~~~~~~~~~~~~~~~.......................................

SUE EAN NT2..-

mnmn 5 to PLA-5620 Proposed Technical Specification Changes (Retyped)

(Units 1 & 2)

PPL Rev. 0 Recirculating Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of Figure 3.4.1-1.

OR One recirculation loop may be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of Figure 3.4.1-1 provided the following limits are applied when the associated LCO is applicable.

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR;

c.

LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),"

single loop operation limits specified in the COLR;

d.

LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; and

e.

Recirculation pump speed is < 80%.

-Note-Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY:

MODES 1 and 2.

SUSQUEHANNA - UNIT 1 TS / 3.4-1 Amendment

PPL Rev. 0 Recirculating Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Total core flow as a function A.1 Place reactor mode switch Immediately of THERMAL POWER within in the shutdown position.

Region I of Figure 3.4.1-1.

OR No recirculation loops operating while in MODE 1.

B. ------

NOTE---------------

B.1 Place the reactor mode Immediately Only applicable when in switch in the shutdown Region II of Figure 3.4.1-1.

position.

Two or more APRM readings oscillating with one or more oscillating 2 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating and deactivating with a period

> 1 second and < 5 seconds.

OR Sustained LPRM oscillations

> 10 wIcm2 peak-to-peak with a period 1 second and

< 5 seconds.

OR Less than 50% of required LPRM upscale alarms OPERABLE.

(continued)

SUSQUEHANNA-UNIT 1 TS /3.4-2 Amendment

PPL Rev. 0 Recirculating Loops Operating 3.4.1 ACTION (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Total core flow as a function C.1 Initiate action to restore Immediately of THERMAL POWER within total core flow as a function Region II of Figure 3.4.1-1.

of THERMAL POWER outside of Region II.

D. Recirculation loop flow D.1 Declare the recirculation 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months mismatch not within limits.

loop with lower flow to be "not in operation."

E.

No recirculation loops in E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation while in MODE 2.

OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA-UNIT 1 Amendment TS/13.4-3

PPL Rev. 0 Recirculating Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 NOTE----

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a.

< 10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b.

5 million Ibm/hr when operating at

> 75 million Ibm/hr total core flow.

SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER is outside of Region I and 11 of Figure 3.4.1-1.

SR 3.4.1.3 NOTE---

Only required to be met during single loop operations.

Verify recirculation pump speed is within the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit specified in the LCO.

SUSQUEHANNA - UNIT 1 TS / 3.4-4 Amendment

PPL Rev. 0 Recirculating Loops Operating 3.4.1 100

.~~ l IOD 11_

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SD~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.

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t/ z e S~~~~~~~~~~~~~~~~~~...

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2~~~~~~~~~~~~~~.

~~~~~~~~~.

~~~~~~~~~~.......

1D

~~~~~~~~~~~~~~~~~.............

~~~~~~~~~~~~~~~...

Core Flow (Million Ibrn/hr)

.~~~~~~~~~~~~~~

Figure 3.4.1-1 Thermal Power Stabil1ity Restri cti ons SUSQUEHANNA - UNIT 1 TS / 3.4-5 Amendment

PPL Rev. 0 Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of Figure 3.4.1-1.

OR One recirculation loop may be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of Figure 3.4.1-1 provided the following limits are applied when the associated LCO is applicable:

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR;

c.

LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),"

single loop operation limits specified in the COLR;

d.

LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; and

e.

Recirculation pump speed is < 80%.

Note-------

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY:

MODES 1 and 2.

SUSQUEHANNA - UNIT 2 Amendment T S I13.4-1

PPL Rev. 0 Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Total core flow as a function A.1 Place reactor mode switch Immediately of THERMAL POWER within in the shutdown position.

Region I of Figure 3.4.1-1.

OR No recirculation loops operating while in MODE 1.

B. -

NOTE B. 1 Place the reactor mode Immediately Only applicable when in switch in the shutdown Region II of Figure 3.4.1-1.

position.

Two or more APRM readings oscillating with one or more oscillating 2 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating and deactivating with a period

> 1 second and < 5 seconds.

OR Sustained LPRM oscillations

> 10 w/cm2 peak-to-peak with a period 1 second and

<5 seconds.

OR Less than 50% of required LPRM upscale alarms OPERABLE.

(continued)

SUSQUEHANNA - UNIT 2 TS 3.4-2 Amendment

PPL Rev. 0 Recirculation Loops Operating 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Total core flow as a C.1 Initiate action to restore Immediately function of THERMAL total core flow as a function POWER within Region II of THERMAL POWER of Figure 3.4.1-1.

outside of Region II.

D.

Recirculation loop flow D.1 Declare the recirculation 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months mismatch not within limits.

loop with lower flow to be "not in operation."

E.

No recirculation loops in E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation while in MODE 2.

OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA - UNIT 2 TS 3.4-3 Amendment

PPL Rev. 0 Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.1.1 I,4' I

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow mismatch with both recirculation loops in operation is:

a.

< 10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b.

< 5 million Ibm/hr when operating at 2 75 million Ibm/hr total core flow.

FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER is outside of Region I and 11 of Figure 3.4.1-1.

SR 3.4.1.3

-NOTE-----

Only required to be met during single loop operations.

Verify recirculation pump speed is within the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit specified in the LCO.

SUSQUEHANNA - UNIT 2 F,

.;

I Kin-rr: -

1 "

TS / 3.4-4 Amendment

PPL Rev. 0 Recirculation Loops Operating 3.4.1 100

.X/S

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90-~ ~

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30 35 40 45 50 55 00 05 70 Core Flow (Million lbm/hr)

Figure 3.4.1-1 Thermal Power Stability Restrictions SUSQUEHANNA - UNIT 2 TS 3.4-5 Amendment to PLA-5629 List of Regulatory Commitments (Units 1 & 2)

LIST OF REGULATORY COMMITMENTS I

REGULATORY COMMITMENTS Due Date/Event There are no new commitments associated with this submittal.

NA

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1--,

- 'j,

ML031330658

Contents

Text

References:

Enclosure:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

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ML031330658

Text

References:

Enclosure:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

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