Text

Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes
	ML042590559
Person / Time
Site:	Susquehanna
Issue date:	09/08/2004
From:	Mckinney B; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PLA-5756
	Download: ML042590559 (62)
	v • d • e

Britt T. McKlnnoy PPL Susquehanna, LLC Vice President-Nuclear Site Operations 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@ pplweb.com PP tM.

SEP 0 8 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 266 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 231 TO LICENSE NPF-22: INCORPORATION OF TSTF-16 AND EDITORIAL CHANGES Docket Nos. 50-387 PLA-5756 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 Units 1 and 2.

The proposed amendment incorporates Technical Specification Task Force (TSTF) 16 and three (3) editorial changes.

These proposed changes have been reviewed by the Plant Operations Review Committee and approved by the Susquehanna Review Committee.

The Enclosure to this letter provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. Attachment 1 provides the existing Technical Specification pages marked-up to show the proposed change. provides revised "Camera Ready" TS pages. Attachment 3 provides the corresponding TS Bases "markup" pages. No new regulatory commitments are made herein.

We request approval of the proposed License Amendment by August 01, 2005, with the amendment being implemented within 60 days following approval.

In accordance with 10 CFR 50.91(b), PPL Susquehanna, LLC is providing the Commonwealth of Pennsylvania with a copy of this proposed License Amendment request.

1kDc) I

Document Control Desk PLA-5756 If you have any questions regarding this submittal, please contact Mr. Neil Coddington at (610) 774-4019.

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

Executed on: Ct e B. T. McKinney

Enclosure:

PPL Susquehanna Evaluation of the Proposed Changes Attachments:

Attachment 1 - Proposed Technical Specification Changes Units 1 & 2, (Mark-ups)

Attachment 2 - Proposed Technical Specification Pages Units 1 & 2, (Camera Ready)

Attachment 3 - Technical Specification Bases Changes, (Provided for Information) cc: NRC Region I Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

Enclosure to PLA-5756 PPL Susquehanna Evaluation of Proposed Change Incorporation of TSTF-16 and Editorial Changes

1. DESCRIPTION

2. PROPOSED CHANGE

3. BACKGROUND

4. TECHNICAL ANALYSIS

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

6. ENVIRONMENTAL CONSIDERATION

7. REFERENCES

Enclosure to PLA-5756 Page 1 of 8 PPL EVALUATION

1.0 DESCRIPTION

This 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.

This amendment request proposes four unrelated changes. These changes are as follows:

(1) Add an Action Note to both the Unit 1 and Unit 2 TS 3.8.7 to address the potential for deenergized Class IE battery chargers. The need for this added restriction was identified by Technical Specification Task Force (TSTF) change TSTF-16 (during Revision 2 changes). The note is added to direct entry into applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources - Operating," for DC sources made inoperable by inoperable AC power distribution subsystems. This Note is reflected in NUREG-1433, "Standard Technical Specifications for General Electric Plants (BWRI4)," Revision 2 (Reference 1). The corresponding TS Bases section is also revised.

(2) Correct several editorial and formatting errors in both Unit 1 and Unit 2 TS to be consistent with NUREG-1433.

(3) Revise the one time 10-day completion time allowance in both Unit 1 and Unit 2 LCO 3.8.1 Condition A for the replacement of Startup transformer No. T-10. The corresponding TS Bases section is also revised.

(4) Correct typographical errors in both Unit 1 and Unit 2 TS 3.3.1.1 and TS 3.3.5.1.

The changes are:

- in Table 3.3.1.1-1 for Function l.b, revise SR 3.3.2.2.15 to SR 3.3.1.1.15.

- in the APT Note in TS 3.3.5.1 revise Function 3.f to Function 3.e.

2.0 PROPOSED CHANGE

The four proposed changes are discussed separately as follows:

(1) Add a Note to Required Action A.1 of both the Unit 1 and Unit 2 SSES TS 3.8.7.

The Note states: "Enter applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources-Operating," for DC source(s) made inoperable by inoperable

Enclosure to PLA-5756 Page 2 of 8 AC electrical power distribution subsystems." This will assure that upon loss of AC power to required battery chargers, the appropriate actions of TS 3.8.4 are entered.

(2) Correct various pages of the Unit 1 and Unit 2 TS Section 3.8, Electrical Power Systems, for editorial and format content. These changes establish consistency with other SSES TS presentations of similar content and consistency with the wording and format presented in NUREG 1433 (Reference 3). The affected Specifications are:

- Unit 1 and Unit 2 TS 3.8.2 Applicability statement format;

- Unit l and Unit 2 TS 3.8.7 Required Actions A.1 and B.1 revise "s" to "(s)";

- Unit 1 TS 3.8.7 Completion Times for Required Actions A.1 and B.1 remove extraneous periods; and

- Unit 1 TS 3.8.8 Applicability statement format.

These changes are consistent with NUREG-1433, "Standard Technical Specifications for General Electric Plants (BWRI4)," Revision 2 (Reference 3).

(3) Revise the one time 10-day completion time allowance in both Unit 1 and Unit 2 LCO 3.8.1 Condition A for the replacement of Startup transformer No. T-10.

(4) Correct typographical errors in both Unit 1 and Unit 2 TS 3.3.1.1 and 3.3.5.1. The changes are:

- in Table 3.3.1.1-1 for Function l.b, revise SR 3.3.2.2.15 to SR 3.3.1.1.15.

- in the APT Note in TS 3.3.5.1 revise Function 3.f to Function 3.e.

Associated TS Bases changes that reflect the intent of the TS changes are also provided for information in an Attachment.

3.0 BACKGROUND

The onsite Class IE AC and DC electrical power distribution system is divided into redundant and independent AC electrical power distribution subsystems and redundant independent DC electrical power distribution subsystems. The safety-related AC distribution system consists of four 4.16 kV Engineered Safeguards System (ESS) buses each having a primary and alternate offsite source of power as well as an onsite diesel generator (DG) source that supports one 4.16 kV ESS bus in each unit.

Enclosure to PLA-5756 Page 3 of 8 Portions of the Unit 1 AC Distribution System are shared between both units, since the common equipment (Emergency Service Water (ESW), Standby Gas Treatment System (SGTS), Control Structure HVAC (CREOAS), etc.) is energized only from the Unit 1 AC Distribution System. As such, some components that are required by Unit 2 receive power through Unit 1 electrical power distribution subsystems. The Unit 1 electrical power distribution subsystems needed to support the required Unit 2 equipment are addressed in Unit 2 LCO 3.8.7, Table 3.8.7-1. Refer to SSES Final Safety Analysis Report (FSAR) Sections 8.1.3 and 8.3.1 for further details and discussion, including references to applicable drawings.

Proposed Change No. 1:

In conjunction with TS LCO 3.0.6, TS 3.8.7 would allow the safety related 480 VAC buses powering the safety related battery chargers to be deenergized for periods of time longer than allowed by TS 3.8.4 (which provides the Actions for inoperable battery chargers). This potential non-conservative allowance was generically identified by the Technical Specification Task Force (TSTF). As a result, an added restriction was identified in TSTF-16 during Revision 2 changes. A note is added to the Unit 1 and Unit 2 Technical Specifications to direct entry into applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources - Operating," for DC sources made inoperable by inoperable AC power distribution subsystems. This Note is also reflected in NUREG-1433, "Standard Technical Specifications for General Electric Plants (BWRI4),"

Revision 2 (Reference 1).

Proposed Change No. 2:

During the conversion to the Improved Technical Specifications several editorial and formatting errors occurred. The correction of these errors is consistent with NUREG-1433, "Standard Technical Specifications for General Electric Plants (BWR/4),"

Revision 2.

Proposed Change No. 3:

In order to provide adequate time for the installation of a replacement for Startup Transformer T-10, a one-time 10-day completion time allowance was requested and granted. Startup Transformer T-10 was replaced on October 18, 2003. Therefore, the one-time allowance is no longer applicable.

Proposed Change No. 4:

Several typographical errors were introduced during the initial production of the Improved Technical Specifications (Table 3.3.1.1-1) and the production of an amendment to TS LCO 3.3.5.1.

Enclosure to PLA-5756 Page 4 of 8

4.0 TECHNICAL ANALYSIS

Proposed Change No. 1:

The request also adds a Note to Required Action A.1 for both the Unit 1 and Unit 2 SSES TS 3.8.7 stating: "Enter-applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources-Operating," for DC source(s) made inoperable by inoperable AC electrical power distribution subsystems." This added requirement will address the potential for deenergized Class IE battery chargers, which was identified by Technical Specification Task Force (TSTF) change TSTF-16 (during Revision 2 changes), and incorporated into NUREG-1433, Revision 2 (Reference 1).

TS 3.8.7 Condition A, associated with the added Note, applies to one or more AC electrical power distribution subsystems inoperable (i.e., deenergized) and would allow 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore the inoperable subsystem. Inoperability of a distribution subsystem can result in loss of charging power to batteries and eventual loss of DC power. The added Note ensures that the appropriate attention is given to restoring charging power to batteries (in accordance with the Actions of TS 3.8.4), as necessary, after loss of distribution systems. The current SSES TS 3.8.4 Actions for an inoperable battery charger impose 2-hour restorative and/or compensatory action. As such this change imposed more conservative actions appropriate to enhancing the safe and reliable operation of the facility.

Proposed Change No. 2:

Several proposed editorial and formatting corrections are consistent with NUREG-1433, "Standard Technical Specifications for General Electric Plants (BWR/4)," Revision 2 (Reference 3).

Proposed Change No. 3:

The one time completion time allowance is no longer applicable since Startup Transformer T-10 was replaced on October 18, 2003. Deletion of this one time allowance does not affect the Technical Specifications or the operation of SSES.

Proposed Change No. 4:

Correction of the typographical errors does not have any effect on the technical contents of the Technical Specifications nor does it cause any other document or procedure to be revised.

Enclosure to PLA-5756 Page 5 of 8 Based on the above evaluation, (1) there is reasonable assurance that the health and safety of the public will 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 This No Significant Hazards Consideration evaluates the following changes to the Technical Specifications:

(1) Add a Note to Required Action A.1 of both the Unit 1 and Unit 2 SSES TS 3.8.7.

The Note states: "Enter applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources-Operating," for DC source(s) made inoperable by inoperable AC electrical power distribution subsystems."

(2) Correct various pages of the Unit 1 and Unit 2 TS Section 3.8, Electrical Power Systems, for editorial and format content. The affected Specifications are:

- Unit 1 and Unit 2 TS 3.8.2 Applicability statement format;

- Unit 1 and Unit 2 TS 3.8.7 Required Actions A.1 and B.1 revise "s" to "(s)";

- Unit 1 TS 3.8.7 Completion Times for Required Actions A.1 and B.1 remove extraneous periods; and

- Unit 1 TS 3.8.8 Applicability statement format.

(3) Revise the one time 10-day completion time allowance in both Unit 1 and Unit 2 LCO 3.8.1 Condition A for the replacement of Startup transformer No. T-10.

(4) Correct typographical errors in both Unit 1 and Unit 2 TS 3.3.1.1 and 3.3.5.1. The changes are:

- in Table 3.3.1.1-1 for Function 1.b, revise SR 3.3.2.2.15 to SR 3.3.1.1.15.

- in the APT Note in TS 3.3.5.1 revise Function 3.f to Function 3.e.

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-5756 Page 6 of 8

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

Response: No.

The Technical Specification allowed Completion Time for any inoperability is not an initiator to any accident sequence analyzed in the Final Safety Analysis Report (FSAR). The changes do not involve any physical change to structures, systems, or components (SSCs) and does not alter the method of operation or control of SSCs.

The current assumptions in the safety analysis regarding accident initiators and mitigation of accidents 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 AC distribution system and supported equipment functions remain capable of performing the function as described in the FSAR. Therefore, the mitigative functions supported by the system will continue to provide the protection assumed by the analysis.

The correction of typographical errors, changes in format and the deletion of a no longer required one-time exemption are administrative changes.

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, at which protective or mitigative actions are initiated, affected by this change. This change will not alter the manner in which equipment operation is initiated, nor will the function 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. The correction of typographical errors, changes in format and the deletion of a no longer required one-time exemption are administrative changes. 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-5756 Page 7 of 8

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 restoration times for deenergized AC distribution subsystems has been previously evaluated in Unit 2 Amendment No. 148. Additional margin of safety is gained with the inclusion of the requirement to enter applicable actions for inoperable Class lE battery chargers as a result of inoperable AC bus(es). The correction of typographical errors, changes in format and the deletion of a no longer required one-time exemption are administrative changes. Therefore the plant response to analyzed events will continue to provide the margin of safety assumed by the analysis.

5.2 Applicable Regulatory Requirements/Criteria SSES FSAR Sections 3.1 and 3.13 provide detailed discussion of SSES compliance with the applicable regulatory requirements and guidance. The proposed TS amendment:

(a) Does not alter the design or function of any system; (b) Does not result in any change in the qualifications of any component; and (c) Does not result in the reclassification of any component's status in the areas of shared, safety related, independent, redundant, and physically or electrically separated.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will 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.

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

Enclosure to PLA-5756 Page 8 of 8 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 changes 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 changes do 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.

7.0 REFERENCES

1. NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4," Revision 2, dated June 2001.

Attachment 1 to PLA-5756 Proposed Technical Specification Changes Units 1 & 2 (Mark-ups)

7 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................. 1.1-1 1.1 Definitions........................................1...................... 1.1-1 1.2 Logical Connectors ................. 1.2-1 1.3 Completion Times ................. 1.3-1 1.4 Frequency...................................................1........................................ 1.4-1 SA E Y L M T S s .................................................................... T 2.0 2.0 SAFETY LIMITS (SLs) ................. TS/2.0-1 2.1 SLs. :TS/2.0-1 2.2 SL Violations............................................................T/......................TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .... 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 ............................................. 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 (§LC) System .3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves .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 .1 3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation .............. 1 '.3-1 3.3.1.2. Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 I

3.3.2.1 Control Rod Block Instrumentation ........................ :.'.;.;::. 3.';:'3-.16 2.. -

3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation .3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .3.3-23 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 ........... -36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ......... 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 (continued)

UNIT 11 TSITOC-1 Amendment +B-*5-SUSQUEHANNA - UNIT SUSQUEHANNA - TS / TOC - 1 Amendment 213,-215-

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation ........................................... 3.3-67 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ........................................... 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ........................................... 3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS) ........................... TSI3.4-1 3.4.1 3.4.2 Recirculation Loops Operating ...........................

Jet Pumps ...........................

TS/3.4-1 3.4-6 I

3.4.3 Safety/Relief Valves (S/RVs) ............................... 3.4-8 3.4.4 RCS Operational LEAKAGE ............................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ............................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ............................... 3;4-14 3.4.7 RCS Specific Activity ............................... 3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ............................ 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ............................... 3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits ................................ ;.3.4-24 3.4.11 Reactor Steam Dome Pressure ............................... 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM . ....................................

3.51 5

3.5.1 ECCS - Operating ............................................ 3.5-1

-3;5.2 -ECCS -Shutdown............................................................................3.5-8 3.5.3 RCIC System .................................................................................... 3.5-12 3.6 CONTAINMENT SYSTEMS ............................................ 3.6-1 3.6.1.1 Primary Containment ............................................ 3.6-1 3.6.1.2 Primary Containment Air Lock ............................................ 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................. TS/3.6-8 3.6.1.4 Containment Pressure ............................................ 3.6-17.

3.6.1.5 Drywell Air Temperature ............................................ 3.6-18 3.6.1.6 ;Suppression-Chamber-to-Drywell Vacuum Breakers . . 3.6-19 3.6.2.1 Suppression Pol Average Temperatr. ... . .......3.6-22 3.6.2.2 Suppression Pool Water Level ................................ 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .. TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray................... 3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners ................................. ;.3.6-30 3.6.3.2 Drywell Air Flow System ................................ 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration ................................ 3.6-34.

3.6.4.1 Secondary Containment ................................ 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................... 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System................................... 3.6-42.

(continued)

UNIT II TSITOC-2 Amendment 1-9 2+5 SUSQUEHANNA -UNIT SUSQUEHANNA -

TS /TOC -2 Amendment-2+3,2t5

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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 ....... Ia-8-1 3.8.1 AC Sourcess-Operating ......

3.8.2 AC Sources - Shutdown ... ................... :.:......-17J 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 ....................................................... ....

3.8.7 Distribution Systems - Operating -------.----.----..----- -----. C.....3.8-37 3.8.8 Distribution Systems - Shutdown.......................................

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 .3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation. 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .3.10-4 3.10.3 Single Control Rod W0ithdrawal - 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 . .....................

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....................................................................................4.01 4.1 Site Location ....... ; 4.0-1 4.2 Reactor Core. 4.0-1 4.3 Fuel Storage........................................................................................04. 1 (continued)

SUSQU.E. HAN.N. A- UNI. I . O - Am n.ST m n 2 -

SUSQUEHANNA - UNIT TS /TOC -3 Amendmentz"+,*+&

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility...................... 5.0-1 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications...................... 5.0-5 5.4 Procedures ...................... ; 5.0-6 5.5 Programs and Manuals ...................... 5.0-7 5.6 Reporting Requirements. ...................... 5.0-19 5.7 High Radiation Area ...................... 5.0-27 NFM TS1 text TOC.doc I SUSQUEHANNA- UNIT 1 TS /TOC -4 Amendment zN-3-, 24 PPL Rev.1g2 RPS Instrumentation

3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPUCABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 11221125 divisIons Flux-High SR 3.3.1.1A of fun scale SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 SO° 3 H SR 3.3.1.1.1 s 122/125 divislons SR 3.3.1.1.5 of fun scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 3 H SR 3.3.1.1.5 NA SR 8:3:2:21t'

3. 3 - /./1

2. Average Power Range Monitors

a. Neutron 2 2 G SR 3.3.1.1.1 . s 20% RTP Flux-High. SR 3.3.1.1A Setdown SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15

b. Flow Biased 1 2 F SR 3.3.1.1.1 s0.58W Simulated SR 3.3.1.1.2 + 62% RTP) and Thermal SR 3.3.1.1.3 S115.5%RTP '

Power-High SR 3.3.1.1.8

- -:- -SR 3.3.1.1.9 _

SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 (a) With any control rod withdrawn from a core cell containing one or more fuel assembbles.

(b) 0.58 W + 57% RTP when reset for single loop operation per LCO 3.4.1, 'Redrculation Loops Operafing.1 SUSQUEHANNA - UNIT 1 -r.5/3.3-7 Ampridment 474--

PPL Revue ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

--- NOTES

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3. and' (b)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3p~rovided the associ ted Function or the redundant Functiori maintains ECCS initiation capabity. -

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 A test of all required contacts does not have to be' performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA-UNIT 1 7-5/ 3.3-41 Amendment V:9: . -

PPL Rev.,.

AC Sources - Operating

3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore offsite circuit to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months status.

AND I

.6 days from discovery of failure to meet LCO 10 dzays for a~c timro outage kor .Uacr et of Startup T~cfez Nlumber l0 toc Dczcmber 31, 2033.

B. One required B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG inoperable. OPERABLE offsihe circuits.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s), 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of supported by the inoperable DG, Condition B concurrent, inoperable when the redundant with inoperability of required feature(s) are inoperable. redundant required feature(s)

AND (continued)

SUSQUEHANNA - UNIT 1 TS/3.8-2 Amendment 1/8

-244-

PPL Rev.,,e AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class lE AC electrical power distribition subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown"; and

.b. Two diesel generators (DGs) capable of supplying the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5, and During movement of irradiated fuel assemblies in the

[eondary containment.

- t7---_-

SUSQUEHANNA - UNIT 1 -r-513.8-17 Amendment #t&

PPL Rev.,&e Distribution Systems - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The electrical power distribution subsystems in Table 3.8.7-1 shall be OPERABLE.

APPLICABILITY ': MODES 1, 2, and 3.

ACTIONS

, _1I~~5I 4,

CONDITION REQUIRED ACTION COMPLETION TIME A. -- N OT E A.1 Restore Unit 1AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Not applicable to DG E power distribution DC electrical power subsystems to OPERABLE AND subsystem. status. (S)

One or more Unit 1 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery AC electrical power of failure to meet LCO distribution 3.8.7 except for subsystems Condition D or inoperable.

B. - NOTE - B.1 Restore Unit 1 DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG E electrical power distribution DC electrical power subsystems to OPERABLE AND subsystem. status. (5)

One or more Unit 1 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery DC electrical power of failure to meet distribution LCO 3.8.7 except for subsystems Condition D or §)

inoperable.

(continued)

SUSQUEHANNA - UNIT 1 7-5/3.8-37 Amendment t-&

INSERT "A.1" (UI: pg 3.8-37)

NOTE-Enter applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources - Operating," for DC source(s) made inoperable by inoperable power distribution subsystem(s).

PPL Rev.e Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems-Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems listed in Table 3.8.7-1 shall be OPERABLE to support equipment required to be OPERABLE.

- I APPLICABILITY: MODES 4 and 5.During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

-- I-L-J----NU -_

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. -NOTEA.1 Declare associated Immediately Not applicable to DG E supported required DC electrical power feature(s) inoperable.

subsystem.

OR One or more required AC or DC electrical power distribution subsystems inoperable. - -

(continued)

SUSQUEHANNA- UNIT I _rS1 3.8-41 Amendment*76-

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................................................ 1.1-1 1.1 Definitions ................................................ 1.1-1 1.2 Logical Connectors ................................................ 1.2-1 1.3 Completion Times ................................................ 1.3-1 1.4 Frequency................................................ 1.4-1 2.0 SAFETY LIMITS (SLs) ..................................................TSI2.01 2.1 SLs ................................................ TS/2.0-1 2.2 SL Violations ................................................ TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ........................TS/3.04 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 .................. 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 ................... 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 ............................................. .3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ...................... 3.3- 1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.2.1 Control Rod Block Instrumentation ............................................. 3.3-16 3.3.2.2. Feedwater- Main Turbine High Water Level Trip Instrumentation .......... ;.;.;.;.;:.3;3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .3.3-23 3.3.3.2 Remote Shutdown System.3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation .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 Instrumentation ................................... 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 TSITOC -1 Amendment 44g 40e-

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ........................ ............ 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring......................................................................................... 3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS) ...........................TS/3.4-1 3.4.1 3.4.2 Recirculation Loops Operating ...........................

Jet Pumps ...........................

TS/3.4-1 3.4-6 I

3.4.3 Safety/Relief Valves (S/RVs) ........................... 3.4-8 3.4.4 RCS Operational LEAKAGE ............................... , 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ............................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ............................... 3.4-14 3.4.7 RCS Specific Activity............: ..... 3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ............................ 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ............................... 3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits ............................... 3.4-24 3.4.11 Reactor Steam Dome Pressure ............................... 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLIN4G (RCIC) SYSTEM ................................. 3.5-1 3.5.1 ECCS - Operating ........... 3.5-1 3.5.2 ECCS - Shutdown ........... 3.5-8 3.5.3 RCIC System ........... 3.5-12 3.6 CONTAINMENT SYSTEMS ......... .................................. 3.6-1 3.6.1.1 Primary Containment ........................................... 3.6-1 3.6.1.2 Primary Containment Air Lock .............. ............................. 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................ TS/3.6-8 3.6.1.4 Containment Pressure ........................................... 3.6-17 3.6.1.5 Drywell Air Temperature ......... .................................. 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers .......... .............. 3.6-19 3.6.2.1 Suppression Pool Average Temperature .......................................... 3.6-22 3.6.2.2 Suppression Pool Water Level ........................................... 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .. 3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners .................................. 3.6-30 3.6.3.2 Drywell Air Flow System ....................................... 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration ..................................... 3.6-34 3.6.4.1 Secondary Containment ...... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ....................................... 3.642 (continued)

EHA NA TS/TOC UNISIT C-2A men men 48 ~ 49 SUSQUEHANNA - UNIT 22 SUSQ -2 Amendment

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ................................ TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) .... TSI3.7-1 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 .......................... ;.,..3.;

3.8.1 AC Sources - Operating .............................. ; .

3.8.2 AC Sources - Shutdown ............................. U..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 Cell Parameters .......... 3.8-39.

3.8.7 Distribution Systems - Operating.............................................. Z/ 1 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 ............................... 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation............................ 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ............................... 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ............................... 3.10-8 3.10.4 Single Control Rod Withdrawal - Cold Shutdown .............................. 3.10-9 3.10.5 Single Control Rod Drive (CRD) Renibivai - 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 Site Location ............................... TS/4.0-1 4.2 Reactor Core....................................................................................TS/4.0-1 4.3 Fuel Storage......................................................................................TS/4.0-1 (continued)

SUSQUEHANNA - UNIT 2 TS/TOC - 3 Amendment4g&,49a

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ....................... : 5.0-1 5.1 Responsibility ...................... 5.0-1 5.2 Organization ................ ; 5.0-2

.5.3 Unit Staff Qualifications.5.0-5 5.4 Procedures ................ 5.0-6 5.5 Programs and Manuals .5.0-7 5.6 Reporting Requirements .5.0-19 5.7 High Radiation Area .TS/5.0-24 NFM TS2 Text TOC.doc SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 48,9

PPL Rev.f RPS Instrumentation 3.3.1.1 Table 3.3.1.1.1 (page I of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS OTHER REQUIRED REFERENCED SURVEILLANCE ALLOWABLE SPECIFIED CHANNELS PER ACTION D.1 REQUIREMENTS VALUE FUNCTION CONDITIONS TRIP SYSTEM

1. Intermediate Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 s122i125divsions Flux-High SR 3.3.1.1 of llscae SR 3.3.1.1.

SR 3.3.1.1.7 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 5(" 3 H SR 3.3.1.1.1 t1221125divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop .2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 3 H SR 3.3.1.1.5 NA SR ; 2+/-i 3.3./.I. 1.5

2. Average Power Range Monitors

a. Neutron 2 2 G SR 3.3.1.1.1 S20 RTP.

Flux-High, SR 3.3.t1.tA Setdown SR 3.3.1.1.7 SR 3.3.1.1.8 -

SR 3.3.1.1.11 SR 3.3.1.1.15 b.FlowBiased 1 2 F SR 3.3.1.1.1 S0S8W Simulated SR 3.3.1.12 + 62% RTP> and Thermal SR 3.3.1.1.3 s115.5%RTP Power-High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.58 W + 57% RTP when reset for single loop operation per LCO 3.4.1, Recirculation Loops Operating.'

SUSQUEHANNA - UNIT 2 -r-/3.3-7 Amendment 54

PPL Rev.{f ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS D.IPcr INL I I I- 1t

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.f and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3XprQy£dd the asso-iited Function or the redundant Function maintains ECCS initiation capab~if., e SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months

'Z . . .

SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL-TEST. - - 24 months: -

SUSQUEHANNA - UNIT 2 TS /3.3-42 Amendment No. 6,

PPL Rev."?

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power available discovery of no offsite inoperable'when the I power to one 4.16 kV redundant required feature(s) ESS bus concurrent are inoperable. with inoperability of redundant required feature(s).

AND A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

'~- AND I 6 days from discovery of failure to meet LCO 144aysiron""e-epleeement-of StarupTanf 11 1 r Noumber 10 to be zcompleted-by D.c.o 31. D~,

2003.

(continued) --

SUSQUEHANNA - UNIT 2 TS /3.8-2 AmendmentI

I PPL Rev.,e AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown"; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

c. One qualified circuit between the offsite transmission network and the Unit 1 onsite Class I E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown; and

d. The DG(s) capable of supplying the Unit 1 onsite Class 1E electrical power distribution subsystems required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5,-asd Duriqg movement of irradiated fuel assemblies in the secondary ountainment.

E >se~

SUSQUEHANNA - UNIT 2 7:/3.8-19 Amendment 4:54

KPi. /A.- /

Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7. Distribution Systems -Operating LCO 3.8.7 The electrical power distribution subsystems in Table 3.8.7-1 shall be OPERABLE.

I APPLICABILITY: MODES 1. 2. anc1 3. .

r'-I rL I

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Restore Unit 2 AC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Not applicable to DG E electrical power DC Bus OD597. distributionr . AND subsystem4-'to-OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from One or more Unit 2 AC discovery of electrical power failure to meet distribution LCO 3.8.7 except subsystems inoperable. for Condition E or F B. --------- NOTE--------- B.1 Restore Unit 2 DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG E electrical power DC Bus OD597. di stri buti on AND subsystems to OPERABLE/status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from One or more Unit 2 DC / discovery of electrical power sfailure to meet distribution LCO 3.8.7 except subsystems inoperable. for Condition E or F C. One or more Unit 1 AC C.1 Restore Unit 1 AC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months electrical power electrical power distribution distribution subsystems inoperable. subsystem to OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 ., 8[3.8-44 Amendment-1-51

INSERT "A.1 " (U2: pg 3.8-44)

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

Enter applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources - Operating," for DC source(s) made inoperable by inoperable power distribution subsystem(s).

Attachment 2 to PLA-5756 Proposed Technical Specification Pages Units I & 2

("Camera Ready")

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................. 1.1-1 1.1 Definitions ..................... 1.1-1 1.2 Logical Connectors ................. 1.2-1 1.3 Completion Times ................. 1.3-1 1.4 Frequency ................. 1.4-1 2.0 SAFETY LIMITS (SLs) ........... TS/2.0-1 2.1 SLs .. I. TS/2.0-1 2.2 SL Violations .. TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .... 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 .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 ................... 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 3.3.2.1 Control Rod Block Instrumentation ....................... 3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation. 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation; 3.3-23 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 ........... TS/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 .TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation. 3.3-63 (continued)

SUSQUEHANNA -UNIT I TS/ TOC- I Amendment?g3, 2A5

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation...............................................................3.3-67 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ........................................... 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ........................................... 3.3-75

.3.4 REACTOR COOLANT SYSTEM (RCS) ............................................. TS/3.4-1 3.4.1 Recirculation Loops Operating ........................................... TSI3.4-1 3.4.2. Jet Pumps ........................................... 3.4-6 3.4.3 Safety/Relief Valves (S/RVs) ........................................... 3.4-8 3.4.4 RCS Operational LEAKAGE ............................................ 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ........................................... 3.4-14 3.4.7 RCS Specific Activity ........................................... 3.4-17 "3.4.8 Residual Heat Removal (RHR) Shutdown Cooling -

System - Hot Shutdown ........................................ 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ........................................ 3.4-22 3.4.10 RCS Pressure and Temperature (PIT) Limits .................................... 3.4-24 3.4.11 Reactor Steam Dome Pressure ........................................ 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ..................................... 3.5-1 3.5.1 ECCS - Operating ........................................... 3.5-1 3.5.2 ECCS - Shutdown ........................................... 3.5-8 3.5.3 RCIC System ........................................... 3.5-12 3.6 CONTAINMENT SYSTEMS ........................................... 3.6-1 3.6.1.1 Primary Containment ........................................... 3.6-1 3.6.1.2 Primary Containment Air Lock ........................................... 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................ TS/3.6-8 3.6.1.4 Containment Pressure ........................................... 3.6-17 3.6.1.5 Drywell Air Temperature ....................................... 3.6-18_.

3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers .3.6-19 3.6.2.1 Suppression Pool Average Temperature. 3.6-22 3.6.2.2 Suppression Pool Water Level .3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .................... 3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners .................................. 3.6-30 3.6.3.2 Drywell Air Flow System ......................................... 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration .................................... 3.6-34 3.6.4.1 Seconidary Containment ......................................... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ......................................... 3.6-42 (continued)

TS / TOC -2 ment2,5 SUSQUEHANNA UNIT 11 SUSQUEHANNA-- UNIT TS/TOC-2 Amendment 2",yF5

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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 Conrtrol Room Floor Cooling System ........................................ 3.7-10 3.7.5 Main Condepser 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 ............................... 3.8-1 3.8.1 AC Sources - Operating ................................ , TS/3.8-1 3.8.2 3.8.3 AC Sources - Shutdown ...............................

Diesel Fuel Oil, Lube Oil, and Starting Air . ......................

TSt3.8-17 TS/3.8-20 I

3.8.4 DC Sources - Operating ................ ;3.8-23 3.8.5 DC Sources - Shutdown .. 3.8-29 3.8.6 Battery Cell Parameters ...................... 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 ........................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation . ...................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 Site Location .4.0-1 4.2 Reactor Core. 4.0-1 4.3 Fuel Storage . .4.01 (continued)

SUSQUEHANNA - UNIT 1 TS /TOC -3 Amendment 2,f3. g;

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ..................... 5.0-1 5.1 Responsibility..................................5...................................................... 5.0-1 5.2 Organization ............... 5.0-2 5.3 Unit Staff Qualifications ............... 5.0-5 5.4 Procedures ......................................... 5.0-6 0....................................

5.5 Programs and Manuals ................ 5.0-7 5.6 Reporting Requirements ................ 5.0-19 5.7 High Radiation Area ................ 5.0-27 LDCN3556 TS1 texd TOC

. _ . - . . - -. - F . - I . ... _- . t. . , -.... _ .,

SUSQUEHANNA - UNIT 1 TS/TOC-4 Amendment 2Y3, yV5

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 51221125 diisions Flux-High SR 3.3.1.1.4 of full scale SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.1

122/125 divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) H SR 3.3.1.1.5 NA 3

SR 3.3.1.1.15 I

2. Average Power Range Monitors

a. Neutron 2 2 G SR 3.3.1.1.1

20% RTP Flux-High, SR 3.3.1.1.4 Setdown SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15

b. Flow Biased 1 2 F SR 3.3.1.1.1 *0.58W Simulated SR 3.3.1.1.2 + 62% RTPb) and Thermal SR 3.3.1.1.3

115.5% RTP Power-High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.58 W + 57% RTP when reset for single loop operation per LCO 3.4.1, 'Recirculation Loops Operating."

SUSQUEHANNA - UNIT 1 TS /3.3-7 Amendment 1--8,

PPL Rev.

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

NOTES-----------------------------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.e; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.e provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 ----------------------------------- --------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 1 TS /3.3-41 Amendment 17A

PPL Rev.

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore offsite circuit to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months status.

AND I 6 days from discovery of failure to meet LCO I

I B. One required B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG inoperable. OPERABLE offsite circuits.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s), 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of supported by the inoperable DG, Condition B concurrent inoperable when the redundant with inoperability of required feature(s) are inoperable. redundant required feature(s)

AND (continued)

SUSQUEHANNA - UNIT 1 TS /3.8-2 Amendment 1/f 274

PPL Rev.

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown"; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5 During movement of irradiated fuel assemblies in the secondary containment.

SUSQUEHANNA- UNIT 1 T S /3.8-1 7 Amendment 1/8

PPL Rev.

Distribution Systems - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The electrical power distribution subsystems in Table 3.8.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

NOTE--------------- ----------------NOTE--------------------- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months I Not applicable to DG E DC Enter applicable Conditions and electrical power subsystem. Required Actions of LCO 3.8.4, UDC AND

.--.Sources - Operating," for DC source(s) made inoperable by inoperable power distribution subsystem(s).

A. One or more Unit 1 AC A.1 Restore Unit 1 AC electrical 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery electrical power power distribution of failure to meet LCO distribution subsystems subsystem(s) to OPERABLE 3.8.7 except for l inoperable. status. Condition D or E B. -----------NOTE------------- B.1 Restore Unit 1 DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG E power distribution DC electrical power subsystem(s) to OPERABLE AND I subsystem. status.

One or more Unit 1 DC 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery electrical power of failure to meet distribution subsystems LCO 3.8.7 except for inoperable. Condition D or E I (continued)

SUSQUEHANNA-UNIT 1 TS /3.8-37 Amendment 11-4

PPL Rev.

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems-Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems listed in Table 3.8.7-1 shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 4 and 5, I During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

-NOTE-LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. -----------NOTE-------------- A.1 Declare associated Immediately Not applicable to DG E supported required DC electrical power feature(s) inoperable.

subsystem.

OR One or more required AC or DC electrical power distribution subsystems inoperable.

(continued)

SUSQUEHANNA- UNIT 1 TS / 3.8-41 Amendment 1/8

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................. 1.1-1 1.1 Definitions ................. : 1.1-1 1.2 Logical Connectors ................ 1.2-1 1.3 Completion Times ................ 1.3-1 1.4 Frequency ................ 1.4-1 2.0 SAFETY LIMITS (SLs) .................. TS/2.0-1 2.1 SLs ................ TS/2.0-1 2.2 SL Violations.........................................................S......................TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .............. 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 3.1.2Reactvity .......... 3.1-5 nomales....................................................................31-3.1.3 Control Rod OPERABILITY .................. 3.1-7 3.1.4 Control Rod Scram Times ....................... 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 ................... 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 3.3.2.1 --Control Rod Block Instrumentation .3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation .................................. 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .............................. 3.3-23 3.3.3.2 Remote Shutdown System .................................. 3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation .. 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 Instrumentation ................................... 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)

S/TO -1Amenmen 1~, lA 22 SUSQEHANA Amendment 108, too

-UNI SUSQUEHANNA - UNIT TS/TOC - 1

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ........................................... 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ........................................... 3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS)............................................... TS/3.4-1 3.4.1 Recirculation Loops Operating ........................................... TSI3.4-1 3.4.2 Jet Pumps ........................................... 3.4-6 3.4.3 Safety/Relief Valves (S/RVs) ........................................... 3.4-8 3.4.4 RCS Operational LEAKAGE ........................................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation .......................................... 3.4-14.

3.4.7 RCS Specific Activity ........................................... 3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................... 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ........................................... 3.4-22 3.4.10 RCS Pressure and Temperature (PIT) Limits .................................... 3.4-24 3.4.11 Reactor Steam Dome Pressure ........................................... 3:4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ..................................... 3.5-1 3.5.1 ECCS - Operating ........................................... 3.5-1 3.5.2 ECCS - Shutdown ........................................... 3.5-8 3.5.3 RCIC System ........................................... 3.5-12 3.6 CONTAINMENT SYSTEMS ........................................... 3.6-1 3.6.1.1 Primary Containment ........................................... 3.6-1 3.6.1.2 Primary Containment Air Lock........................................... 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................ TS/3.6-8 3.6.1.4 Containment Pressure ........................................... 3.6-17 3.6.1.5 Drywell Air Temperature ........................................... 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers ........................ 3.6-19 3.6.2.1 Suppression Pool Average Temperature .......................................... 3.6-22

-3.6.2.2 -Suppression Pool Water Level.. .......................................

3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray.................... 3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners .................................. 3.6-30 3.6.3.2 Drywell Air Flow System ........................................... 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration .................................... 3.6-34 3.6.4.1 Secondary Containment ........................................... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ............................................ 3.6-42 (continued)

_ _~t

=STO- 8 SUSQUEHANNA UNIT 2 SUSUEHNN - UNI 2 TS/TOC - 2 Amendment I do", 1P0 7

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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 Ofigas ........................................... 3.7-13 3.7.6 Main Turbine Bypass System ............... I TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level ............................ 3.7-17 3.8 ELECTRICAL POWER SYSTEMS ............................................. 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 . . TS3.8-23 3.8.4 DC Sources - Operating .. ........................... 3.8-26 3.8.5 DC Sources - Shutdown. ;.;...................... 3.8-34.

3.8.6 Battery Cell Parameters .................................. 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. 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation.3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .3.104

.103- -- Single Control Rod Withdrawal - Hot Shutdown ............ ................

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 Site Location ............. TS/4.0-1 4.2 Reactor Core ............. TS/4.0-1 4.3 Fuel Storage ............. TS/4.0-1 (continued)

UNIT 22 TS/TOC-3 Amendment 18, I0 SUSQUEHANNA - UNIT SUSQUEHANNA - TS/TOC -3 Amendment 1.88, 1,00

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ..................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ..................... 5.0-2 5.3 Unit Staff Qualifications ..................... 5.0-5 5.4 Procedures ..................... 5.0-6 5.5 Programs and Manuals ..................... 5.0-7 5.6 Reporting Requirements ..................... 5.0-19 5.7 High Radiation Area ..................... TS/5.0-24 LDCN3665 TS2 Text TOC

,_V . , , n ... - cA SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1P/8, 0

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS OTHER REQUIRED REFERENCED SURVEILLANCE ALLOWABLE FUNCTION SPECIFIED SPCONIFIONS CHANNELS TRIP SYSTEM PER ACTION ACIND D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 S 122/125 divisions Flux-High of full scale SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.1 S 1221125 divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.5 NA SR 3.3.1.1.15 I

2. Average Power Range Monitors

a. Neutron 2 2 G SR 3.3.1.1.1 s 20% RTP Flux-High, SR 3.3.1.1.4 Setdown SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15

b. Flow Biased 1 2 F SR 3.3.1.1.1 S0.58W Simulated SR 3.3.1.1.2 + 62% RTP°b and Thermal SR 3.3.1.1.3 S 115.5% RTP Power-High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.58 W + 57% RTP when reset for single loop operation per LCO 3.4.1, 'Recirculation Loops Operating.'

SUSQUEHANNA - UNIT 2 TS /3.3-7 Amendment 16

PPL Rev.

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

---------------- NOTES--- ---------- -----------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.e; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.e provided the associated Function or the redundant Function maintains ECCS initiation capability.

I SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 ---------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 2 TS /3.3-42 Amendment No. 1V5

PPL Rev.

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power available discovery of no offsite inoperable when the power to one 4.16 kV redundant required feature(s) ESS bus concurrent are inoperable. with inoperability of redundant required feature(s).

AND A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 6 days from discovery of failure to meet LCO I

I (continued)

SUSQUEHANNA - UNIT 2 TS /3.8-2 Amendment 1 19

PPL Rev.

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown"; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

c. One qualified circuit between the offsite transmission network and the Unit 1 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown; and

d. The DG(s) capable of supplying the Unit 1 onsite Class 1E electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5 During movement of irradiated fuel assemblies in the secondary containment.

SUSQUEHANNA - UNIT 2 TS /3.8-1 9 Amendment i di

PPL Rev.

Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The electrical power distribution subsystems in Table 3.8.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

NOTE---------------- ---------------- NOTE--------------------- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Not applicable to DG E DC Bus Enter applicable Conditions and OD597. Required Actions of LCO 3.8.4, "DC AND Sources - Operating," for DC source(s) made inoperable by inoperable power distribution subsystem(s).

A. One or more Unit 2 AC A.1 Restore Unit 2 AC electrical 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from electrical power distribution power distribution subsystems discovery of failure to subsystems inoperable to OPERABLE status. meet LCO 3.8.7 except for Condition EorF B. --------------- NOTE-------------- B.1 Restore Unit 2 DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG .E DC power distribution subsystems Bus OD597 to OPERABLE status.

AND One or more Unit 2 DC 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from electrical power distribution discovery of failure to subsystems inoperable. meet LCO 3.8.7 except for Condition E or F C. One or more Unit 1 AC C.1 Restore Unit 1 AC electrical 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months electrical power distribution power distribution subsystem subsystems inoperable. to OPERABE status.

(continued)

SUSQUEHANNA - UNIT 2 TS /3.8-44 Amendment 1XI

Attachment 3 to PLA-5756 Technical Specification Bases Changes (Provided for Information)

PPL Rev. X AC Sources - Operating B 3.8.1 BASES ACTIONS A.3 (continued)

Completion Times apply simultaneously, and the more restrictive Completion Time must be met.

As in Required Action A.2, the Completion Time allows for an exception to the normal "time zero" for beginning the allowed outage time "lock."

This exception results in establishing the "time zero" at the time the LCO was initially not met, instead of at the time that Condition A was entered.

A temporary Ccmplction.Tfire is wrinlecteu lo ilie Gomwpleliul ii '

requ irements nhpyp (72 h o u ~~f~~ndic'r' n~A of faIct re.LCO)-%Wih-aR-R" , ,

i.u. c ii. Tia Gfio teoCmplert1o i A~~tcr 10 h epudyi.ompietion lw 10 ddp emin Dcfembr 31-, 003 If during the conduct of the prrb p remrinig opernblc AC curccs bc detcrmdned inoperable (on eon iniidu! unit bosi;), cu.,e,it TS iTeuiruilemeitb ppl To ensure a highly reliable power source remains with one required DG inoperable, it is necessary to verify the availability of the required offsite circuits on a more frequent basis: Since the Required Action only specifies "perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action being not met. However, if a circuit fails to pass SR 3.8.1.1, it is inoperable. Upon offsite circuit inoperability, additional Conditions must then be entered.

B.2 Required Action B.2 is'intended to provide assurance that a loss of offslte - -

power, during the period that a DG is inoperable, does not result Ina complete loss of safety function of critical systems. These features are designed with redundant safety related divisions (i.e., single division systems are not included). Redundant required features failures consist of inoperable features associated with a division redundant to the division that has an inoperable DG.

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." In this Required Action the Completion (continued)

SUSQUEHANNA- UNIT 1 TS I B 3.8-9 Revisions

PPL Rev.,{

Distribution Systems-Operating B 3.8.7 BASES LCO subsystem is only considered Inoperable when the subsystem is not (continued) energized to its proper voltage.

APPLICABILITY The electrical power distribution subsystems are required to be OPERABLE in MODES 1, 2, and 3 to ensdre that:

a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of AOOs or abnormal transients; and

b. Adequate core cooling is provided, and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.

Electrical power distribution subsystem requirements for MODES 4 and 5 are covered in the Bases for LCO 3.8.8, "Distribution Systems-Shutdown."

ACTIONS A.1 knotI With one or more required AC buses, load centers, motor control centers, or distribution panels inoperable but not resulting in a loss of safety function, the remaining AC electrical power distribution subsystems are capable of supporting the minimum safety functions necessary to shut down the reactor and maintain it in a safe shutdown condition, assuming no single failure. The overall reliability is reduced, however, because a single failure in the remaining power distribution subsystems could result in the minimum required ESF functions not being supported. Thereforejhe required AC buses, load centers, motor control centers, and distrbution panels must be restored to OPERABLE -

status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The Condition A worst scenario is one division without AC power (i.e.,

no offsite power to the division and the associated DG inoperable). In this Condition, the unit is more vulnerable to a complete loss of AC power. Itis, therefore, imperative that the unit operators' attention be focused on minimizing the potential for loss of power to the remaining division by stabilizing the unit, and on restoring power to the affected division. The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time limit (continued)

SUSQUEHANNA- UNIT 1 -r.,/ B.c 3.8-80 Revision,(Y

PPL Rev.,2 Distribution Systems-Operating B 3.8.7 BASES ACTIONS A.1 (continued) before requiring a unit shutdown in this Condition is acceptable because:

a. There is a potential for decreased safety if the attention of unit operators is diverted from the evaluations and actions necessary to restore power to the affected division to the actions associated with taking the unit to shutdown within th.is time limit.

b. The potential for an event in conjunction with a single failure of a redundant component in the division with AC power. (The redundant component is verified OPERABLE in accordance with Specification 5.5.11, "Safety Function Determination Program (SFDP).")

The second Completion Time for Required Action A.1 establishes a limit on the maximum time allowed for any combination of required distribution subsystems to be inoperable during any single continuous occurrence of failing to meet LCO 3.8.7. If Condition A is entered while, for instance, a DC bus is inoperable and subsequently returned OPERABLE, this LCO may already have been not met for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This situation could lead to a total duration of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , since initial failure of the LCO, to restore the AC distribution system. At this time a DC circuit could again become inoperable, and AC distribution could be restored OPERABLE.

This could continue indefinitely.

Condition A is modified by a Note that states that Condition A is not applicable to the DG E DC electrical power subsystem. Condition D or E is applicable to an inoperable DG E DC electrical power subsystem.

This Completion Time allows for an exception to the normal "time zero" for beginning the allowed outage lime-"clock." This results in establishing the "Ume zero" at the time this LCO was initially not met, Iristead of at the time Condition A was entered. The 16 hour1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months Completion Time is an acceptable limitation on this potential to fail to meet the LCO indefinitely.

The completion time exception is not applicable to Condition D or E because Conditions D and E are only applicable to DG E DC electrical power subsystem.

EX,.

(continued)

SUSQUEHANNA- UNIT 1 -rTl B,,3.8-81 Revision,&

0 INSERT "Bases A.1" (UI: Pq B 3.8-81)

Required Action A.1 is modified by a Note that requires the applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources - Operating," to be entered for DC subsystems made inoperable by inoperable AC electrical power distribution subsystems. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for inoperable DC sources.

Inoperability of a distribution subsystem can result in loss of charging power to batteries and eventual loss of DC power. This Note ensures that the appropriate attention is given to restoring charging power to batteries, if necessary, after loss of distribution systems.

. I7 - . --- :. - I- , -: , ' --- , -.- %-: .. - -.-. . ,

I

AL Kev.,r AC Sources-Operating B 3.8.1 BASES ACTIONS A.3 (continued) and B are entered concurrently. The 'AND' connector between the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 6 day Completion Times means that both Completion Times apply simultaneously, and the more restrictive Completion Time must be met. /

' As in Required Action A.2, the Completion Time allows for an exception to the normal 'time zero" for beginning the allowed outage time "clock."

This exception results in establishing the "time zero" at the time the LCO was initially not met, instead of at the time that Condition A was entered.

A temporr; CompIctio. Timz is connotoiothoompltion lime

' uqirpment saboVe (72 hourz and sixdey from dioo of fielre to meet~LC) "ath an QR" connector. The temporary Completion Timre i iOdays and applies to the Ceplamcent of t115 StyI lupu Teadlore Pumbor 10. Thccm O pletiu,, T;111 r 1 yse Dcember 31, 2b03. IFdueiing Me noCUGLU Ief t preib~ d -Steit:p T Cat_bii aliulXuf the n oejon-an indiiul r 1k 2d;~, Wusiei l TS ieuguirtrres ~cld lely.

B.1 To ensure a highly reliable power source remains with one required DG inoperable, it is necessary to verify the availability of the required offsite circuits on a more frequent basis. Since the Required Action only specifies 'perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action being not met However, if a circuit fails to pass SR 3.8.1.1, it is inoperable. Upon offsite circuit inoperability, additional Conditions must then be entered.

B.2 Required Action B.2 is intended to provide assurance that a loss of offsite power, during the period that a DG is inoperable, does not result in a complete loss of safety function of critical systems. These features are designed with redundant safety related divisions (i.e., single division systems are not included). Redundant required features failures consist of inoperable features associated with a division redundant to the division that has an inoperable DG.

(continued)

SUSQUEHANNA - UNIT 2 TS/B 3.8-9 Revisiona1l

PPL Rev.,0 Distribution Systems-Operating B 3.8.7 BASES (continued)

LCO subsystem is only considered Inoperable when the subsystem is not energized to its proper voltage.

APPLICABILITY The electrical power distribution subsystems are required to be OPERABLE in MODES 1,2, and 3 to ensure that:

a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of AQOs or abnormal transients; and

b. Adequate core cooling is provided, and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.

Electrical power distribution subsystem requirements for MODES 4 and 5 are covered in the Bases for LCO 3.8.8, "Distribution Systems-Shutdown."

ACTIONS A.1 With one or more required AC buses, load centers, motor control centers, or distribution panels inoperable but not resulting in a loss of safety function, the remaining AC electrical power distribution subsystems are capable of supporting the minimum safety functions necessary to shut down the reactor and maintain it in a safe shutdown condition, assuming no single failure. The overall reliability is reduced, however, because a single failure in the remaining power distribution subsystems could result in the minimum required ESF functions not being supported. Therefore, the required AC buses, load centers, motor control centers, and distribution panels must be restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The Condition A worst scenario is one division without AC power (i.e.,

no offsite power to the division and the associated DG inoperable). In this Condition, the unit is more vulnerable to a complete loss of AC power. It is, therefore, imperative that the unit operators' attention be focused on minimizing the potential for loss of power to the remaining division by stabilizing the unit, and on restoring power to the affected division. The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time limit before (continued)

SUSQUEHANNA - UNIT 2 '77V 13 3.8-86 RevisionV

I PPL Rev-,

Distribution Systems-Operating B 3.8.7 BASES (continued)

ACTIONS A.1 (continued) requiring a unit shutdown in this Condition is acceptable because:

a. There is a potential for decreased safety if the attention of unit operators is diverted from the evaluations and actions hecessary to restore power to the affected division to the actions associated with taking the unit to shutdown within this time limit.

b. The potential for an event in conjunction with a single failure of a redundant component in the division with AC power. (The redundant component is verified OPERABLE in accordance with Specification 5.5.11, "Safety Function Determination Program (SFDP).-)

The second Completion Time for Required Action A.1 establishes a limit on the maximum time allowed for any combination of required distribution subsystems to be inoperable during any single continuous occurrence of failing to meet LCO 3.8.7. If Condition A is entered while, for Instance, a DC bus is inoperable and subsequently returned OPERABLE, this LCO may already have been not met for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This situation could lead to a total duration of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , since initial failure of the LCO, to restore the AC distribution system. At this time a DC circuit could again become inoperable, and AC distribution could be restored OPERABLE.

This could continue indefinitely.

Condition A is modified by a Note that states that Condition A is not applicable to the DG E DC electrical power subsystem. Condition E or F is applicable to an inoperable DG E DC electrical power subsystem.

This Completion Time allows for an exception to the normal "time zero" for beginning the allwed outage time "cdock." This results Inestablishing the "time zero" at the time this LCO was initially not met, instead of at the time Condition A was entered. The 16 hour1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months Completion Time is an acceptable limitation on this potential to fail to meet the LCO indefinitely.

The completion time exception is not applicable to Condition E or F because Condition E and F are only applicable to DG E DC electrical power subsystem.

(continued)

SUSQUEHANNA - UNIT 2 73/- B 3.8-87 Revisiong

.0 INSERT "Bases A.1" (U2: pq B 3.8-87)

Required Action A.1 is modified by a Note that requires the applicable Conditions and Required Actions of LCO 3.8.4, 'DC Sources - Operating," to be entered for DC subsystems made inoperable by inoperable AC electrical power distribution subsystems. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for inoperable DC sources.

Inoperability of a distribution subsystem can result in loss of charging power to batteries and eventual loss of DC power. This Note ensures that the appropriate attention is given to restoring charging power to batteries, if necessary, after loss of distribution systems.

PLA-5756, Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes

Contents

Text

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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PLA-5756, Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes

Text

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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