Text

Correction to License and Technical Specification Pages for Susquehanna Steam Electric Station, Units 1 & 2
	ML040330401
Person / Time
Site:	Susquehanna
Issue date:	01/30/2004
From:	; NRC/NRR/DLPM
To:	;
References
	TAC MB6671, TAC MB6672
	Download: ML040330401 (70)
	v • d • e

May 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - MAIN TURBINE BYPASS SYSTEM OPERABILITY REQUIREMENTS (TAC NOS.

MB6671 AND MB6672)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 210 to Facility Operating License No. NPF-14 and Amendment No. 185 to Facility Operating License Nd. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) In response to your application dated October 31, 2002.

The amendments revise SSES 1 and 2 TS requirements for operability of the main turbine bypass system bypass valves. Specifically, Surveillance Requirement 3.7.6 has been revised to test only each required main turbine bypass valve every 31 days.

A copy of our safety evaluation Is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 210 to License No. NPF-14

2. Amendment No. 185 to License No. NPF-22

3. Safety Evaluation cc w/encs: See next page

May 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM (TAC NOS. MB6663 AND MB6664)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment 211 to Facility Operating License No.

NPF-14 and Amendment 186 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated October 30, 2002.

The amendments revise Technical Specifications Section 5.5.7, Ventilation Filter Testing Program," by changing the control room emergency outside air supply system maximum allowed filter train pressure drop from <9.1 inches water gage (wg), to <7.3 inches wg.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 211 to License No. NPF-14

2. Amendment No. 186 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 3, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENT RE: POST-ACCIDENT SAMPLING SYSTEMS (TAC NOS.

MB7998 AND MB7999)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 212 to Facility Operating License No. NPF-1 4 and Amendment No. 187 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 3, 2003.

These amendments delete TS 5.5.3, "Post Accident Sampling," and thereby eliminate the requirements to have and maintain the post-accident sampling systems for SSES, Units 1 and 2. The amendments also address related changes to TS 5.5.2, "Primary Coolant Sources Outside Containment."

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 212 to License No. NPF-14

2. Amendment No. 187 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 5, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENT RE: INTERMITTENT OPENING OF ISOLATED FLOW PATHS AND TIP ISOLATION (TAC NOS. MB6665 AND MB6666)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 213 to Facility Operating License No. NPF-1 4 and Amendment No. 188 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 31, 2002.

These amendments revise Technical Specifications (TSs) Section 3.3.6.1, TPrimary Containment Isolation Instrumentation," to add an ACTIONS Note allowing Intermittent opening, under administrative control, of penetration flow paths that are isolated. Additionally, these amendments revise TSs to breakout the traversing incore probe system isolation as a separate isolation Function with an associated Required Action to Isolate the penetration within'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rather than Immediately Initiating a unit shutdown. As stated in your application, changes to the Bases for TS 3.3.6.1 will be addressed In accordance with TS 5.5.10, TS Bases Control Program."

A copy of our safety evaluation Is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 213 to License No. NPF-14

2. Amendment No. 188 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 10, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: EXTENDED OUTAGE TIME FOR OFFSITE POWER -

SINGLE OCCURRENCE (TAC NOS. MB9903 AND MB9904)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has Issued the enclosed Amendment No. 214 to Facility Operating License No. NPF-14 and Amendment No. 189 to Facility Operating License No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated July 3, as supplemented by letters dated September 9 and 23, 2003.

The amendments change the Technical Specification (TS) to allow a one-time only change to TS 3.8.1, UAC [Alternating Current] Sources - Operating," Action A.3, by extending the required Completion Time for restoration of an inoperable offsite circuit from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 214 to License No. NPF-14

2. Amendment No. 189 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENT RE: REVISED RESPONSE TO GENERIC LETTER 94-02 "LONG-TERM STABILITY SOLUTION" (TAC NOS. MB9008 AND MB9009)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has Issued the enclosed Amendment No. 215 to Facility Operating License No. NPF-14 and Amendment No. 190 to Facility Operating License No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated May 6, as supplemented by letters dated August 12, and September 18, 2003.

The amendments delete Technical Specification (TS) 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," which has not yet been implemented, and revise TS 3.-4.1, "Recirculation Loops Operating," to formally extend the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. In addition, the amendments revise TS 3.4:1 to refer to the power flow map in the core operating limits report and Include a reference in TS 5.6.5. The requirements serves as an Interim solution until plant-specific analyses is completed and the OPRM system and associated TSs are Implemented.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 215 to License No. NPF-14

2. Amendment No. 190 to License No. NPF-22

3. Safety Evaluation cc wencs: See next page

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)................

2.0-1 2.1 SLs................

2.0-1 2.2 SL Violations................

2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY............................ 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 Setpolnts............. 3.2-7 3.3 INSTRUMENTATION.............................................

3.3-1 3.3.1.1 Reactor Protection.System (RPS) Instrumentation............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 3.3.2.1 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) Instrurrientation..................................... 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) InstrUmentation............... 3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation..................................

3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation................................. 3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation............................. 3.3-63 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation..

3.3-67 (continued)

SUSQUEHANNA - UNIT 1 Amendment-1-64, 2.15 SUSQUEHANNA - UNIT 1 I

Amendments 215

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS NOTES-

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION A.

One or more required A.1 Place channel in trip.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable.

Functions 2.a, 2.d, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.d, 6.b, 7.a, and 7.b B.

One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with isolation capability.

capability not maintained.

I (continued)

SUSQUEHANNA-UNIT I TS 3.3-52 Amendment 18, 213

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

6.

Shutdown Cooling System Isolation

a.

Reactor Steam Dome 1,2,3 1

F SR 3.3.6.1.2 s108 psig Pressure -

High SR 3.3.6.1.3 SR 3.3.6.1.5

b.

ReactorVesselWater 3,4.5 2 (c)

J SR 3.3.6.1.1 211.5 Inches Level -

Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

c.

Manual Initiation 3,4.5 1

G SR 3.3.6.1.5 NA

7.

Traversing Incore Probe Isolation

a.

Reactor Vessel Water 1,2.3 2

G SR 3.3.6.1.1 k 11.5 Inches Level -

Low, Level 3 SR 3.3.6.12 SR 3.3.6.1.3 SR 3.3.6.1.5

b.

Drywell Pressure-1.2.3 2

G SR 3.3.6.12 s 1.88 psig High SR 3.3.6.1A SR 3.3.6.1.5 (c)

Only one trip system required In MODES 4 and 5 when RHR Shutdown Cooling System Integrity maintained.

SUSQUEHANNA - UNIT 1 TS / 3.3-62 Amendment 8, Z13

~-

-Recircuafi-ops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified n the COLR.

OR One recirculation loop may be In operation provided the following limits are applied when the associated LCO is applicable with a THERMAL POWER/core flow condition outside of Regions I and I of the Power Flow Map as specified In the COLR.

a.

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

b.

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

single loop operation limits specified In the COLR;

c.

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

single loop operation limits specified In the COLR, and

d.

LCO 3.3.1.13 'Reactor Protection System (RPS) Instrumentation,'

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

e.

Recirculation pump speed Is m 80%.

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

APPIUCABIlITY:

MODES I and 2.

SUSQUEHANNA -UNIT I S

TS /3.4-1 Amendment 1B'8i4, 215

~

-~-~~~-

- - Recirculating-L-oos-Op-eratfg -

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Region I of the Power Flow Map as specified In the COLR.

OR No recirculation loops operating while in MODE 1.

B.

-NONOTE---

B.1 Place the reactor mode Immediately Only applicable when switch In the shutdown in Region 11 of the position.

Power Flow Map as specified In the COLR.

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

OR Two or more LPRM upscale alarms activating and deactivating with a period Ž1 second and 5 seconds.

OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period 1 second and

5 seconds.

(continued)

OR SUSQUEHANNA - UNIT 1 TS / 3.4-2 Amnendment 1d8 15

R ecKUM -t Fg-L-o Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

Less than 50% of required LPRM upscale alarms OPERABLE.

C.

Total core flow as a C.1 Initiate action to restore Immediately function of THERMAL total core flow as a POWER within function of THERMAL Region II of the Power POWER outside of Flow Map as specified Region I.

In the COLR.

D.

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

lower fow to be not In operation."

E.

No recirculation loops E.1 Be In MODE 3.

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

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

SUSQUEHANNA - UNIT 1 TS / 3.4-3 Amendment 1d8 9, 215

--Recirculating Loops Operating--

3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1

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

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

a.

c 10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b.

5 million Ibm/hr when operating at

Ž75 million Ibm/hr total core flow.

SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER Is outside of Region I and 11 of the Power Flow Map as specified In the COLR.

SR 3.4.1.3

-NOTE Only required to be met during single loop operations.

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

SUSQUEHANNA - UNIT 1

.TS 3.4-4 Amendment 8, 1,, 15

Rirc~latnD~LopTperaing ~

3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK

__~_~

SUSQUEHANNA - UNIT 1 TS 3.4-5 Amendment 1 i 14 215

PPL Rev. 0 Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR),' limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable.

APPLICABILITY:

THERMAL POWER 2 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Main Turbine Bypass System A.1 Satisfy the requirements of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable.

LCO or restore Main Turbine Bypass System to OPERABLE status.

AND Requirements of LCO 3.2.2 not met.

B. Required Action and B.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion Time

< 25% RTP.

not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required main 31 days turbine bypass valve.

(continued)

SUSQUEHANNA - UNIT 1 TS / 3.7-15 Amendment 17$,

210

PPL Rev. 0 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 6 days from discovery of failure to meet LCO OR 10 days for a one-time outage for replacement of Startup Transformer Number 10 to be completed by December 31, 2003 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 Q concurrent Inoperable when the redundant with Inoperability of required feature(s) are inoperable.

redundant required feature(s)

AND (continued)

I SUSQUEHANNA-UNIT I TS 3.8-2 Amendment 177/ 214

PPL Rev. 0 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

B.3.1 Determine OPERABLE DGs are 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.7 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DGs.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to entering Condition B B.4 Restore required DG 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 C. Two offsite circuits C.1 Restore one offsite circuit to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Inoperable.

OPERABLE status.

D. One offsite circuit NOTE----

inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.7, "Distribution AND Systems-Operating,' when Condition D is entered with no AC power source to any One required DG 4.16 kV ESS bus.

inoperable.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR D.2 Restore required DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 1 TS 3.8-3 Amnendment 17Y 214

PPL Rev. 0 AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more E1 Restore at least three required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months required DGs DGs to OPERABLE status.

inoperable.

F. Required Action F.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Associated Completion Time of AND Condition A, B, C, D, or E not met.

F.2 Be In MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. One or more offsite G.1 Enter LCO 3.0.3.

Immediately circuits and two or more required DGs inoperable.

OR One required DG and two offsite circuits inoperable.

SURVEILLANCE REQUIREMENTS a-----------NOTE---

-a--A----

Four DGs are required and a DG is only considered OPERABLE when the DG is aligned to the Class 1 E distribution system. DG Surveillance Requirements have been modified to integrate the necessary testing to demonstrate the availability of DG E and ensure ts OPERABILITY when substituted for any other DG. If the DG Surveillance Requirements, as modified by the associated Notes, are met and performed, DG E can be considered available and OPERABLE when substituted for any other DG after performance of SR 3.8.1.3 and SR 3.8.1.7.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power 7 days availability for each offsite circuit.

(continued)

SUSQUEHANNA-UNIT 1 TS /3.8-4 Amendment 17l 214

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 (ODCM) (continued) shall Indicate the date (i.e., month and year) the change was implemented.

PrimaT Coolant Sources Outside Containment 5.52 This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems Include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, Standby Gas Treatment, Scram Discharge, Post Accident Sampling (until such time as a modification eliminates the PASS penetration as a potential leakage path) and Containment Air Monitoring Systems. The program shall Include the following:

I

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 months.

The provisions of SR 3.0.2 are applicable.

Not Used Radioactive Effluent Controls Program 5.5.3 5.5.4 This program conforms to I CFR 0.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably (continued)

SUSQUEHANNA - UNIT I TS

.0-B Amendment No.

I, e9, 212

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:

ESF Ventilation System Standby Gas Treatment System Control Room Emergency Outside Air Supply System Delta P (inches wg)

<13 Flowrate (cfm) 9,090 to 11,110

< 7.3 5,229 to 6,391 I

e. Demonstrate that the temperature differential in the air flow across the heating coils for each of the ESF system Is greater than or equal to the value specified below when tested in accordance with ASME N51 0-1975:

ESF Ventilation System Standby Gas Treatment System Delta T (OF) 17 Flowrate (cfm) 9.090 to 11,110

f. Demonstrate that the heaters for each of the ESF system dissipate the value specified below when tested in accordance with ANSI N510-1975:

ESF Ventilation System Control Room Emergency Outside Air Supply System Wattage (kW) 27to33 5.5.8 Explosive Gas and Storaqe Tank Radioactivity Monitoring Procram This program provides controls for potentially explosive gas mixtures contained In the Main Condenser Offgas Treatment System and the quantity of radioactivity contained In unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures". The program shall.

Include:

a. The limits for concentrations of hydrogen In the Main Condenser Offgas Treatment System and a surveillance (continued)

SUSQUEHANNA-UNIT I TS I15.0-14 Amendment 478, 211

-~~~~~~~~

~

~~~~~~~~~~~~

-.-- Reporting RleqTir re-nt-~ -

5.6 5.6 Reporting Requirements (continued) 5.6.4 Monthly Operatin Reports Routine reports of operating statistics and shutdown experience, Including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the e of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented In the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Speblfication 3.2.1;

2. The Minimum Critical Power Ratio for Specification 3.2.2;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Average Power Range Monitor (APRM) Gain and Selpoints for Specification 3.2.4; and

5. The Shutdown Margin for SpecifIcation 3.1.1.

6. The stability telated regions of.the Power Flow Map for Specification 3.4.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an Initial assumed power level of 1 02 percent of rated power Is specified In a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt Is 100.6% of the rated thermal power level of 34B9 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as Input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM/Tu) as described In the LEFMVTu Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMVTm system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MW.

(continued)

Amendment 186, 4-215 SUSQUEHANNA - UNIT 1 TS /5.0-21

-Reporting Requirements-5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

9. ANF-91-048(P)(A), 'Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model.

10. XN-NF-80-1 9(P)(A), 'Exxon Nuclear Methodology for Bolling Water Reactors.

11. XN-NF-79-71 (P)(A), 'Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors.'

12. EMF-1 997(P)(A), uANFB-10 Critical Power Correlation.'

13. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal PowerAccuracy and Plant Safety While Increasing Operating Power Level Using the LEFMV/u System," Engineering Reports BOP.

14. Caldon, Inc., Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM,/TU or LEFM CheckPlusTu System,", Efigineering Report ER-160P.

15. EMF-85-74(P), "RODEX 2A (WR)

Fuel Rod Thermal-Mechanical Evaluation Model."

16. EMF-CC-074(P)(A), Volume 4, HBWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2."

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (EGGS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, Including any midcycle revisions or supplements, shall be provided upon Issuance for each reload cycle to the NRC.

(continued)

SUSQUEHANNA - UNIT I TS 1 5.0-23 A end entX 168 9, 14 4 9 215

May 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - MAIN TURBINE BYPASS SYSTEM OPERABILITY REQUIREMENTS (TAC NOS.

MB6671 AND MB6672)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 210 to Facility Operating License No. NPF-1 4 and Amendment No. 185 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 31, 2002.

The amendments revise SSES 1 and 2 TS requirements for operability of the main turbine bypass system bypass valves. Specifically, Surveillance Requirement 3.7.6 has been revised to test only each required main turbine bypass valve every 31 days.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 210 to License No. NPF-14

2. Amendment No. 185 to License No. NPF-22

3. Safety Evaluation cc w/encs: See next page

May 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM (TAC NOS. MB6663 AND MB6664)

Dear Mr. Shriver The Commission has issued the enclosed Amendment 211 to Facility Operating License No.

NPF-14 and Amendment 186 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are In response to your application dated October 30, 2002.

The amendments revise Technical Specifications Section 5.5.7, "Ventilation Filter Testing Program," by changing the control room emergency outside air supply system maximum allowed filter train pressure drop from <9.1 inches water gage (wg), to <7.3 inches wg.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included In the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 211 to License No. NPF-14

2. Amendment No. 186 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 3, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: POST-ACCIDENT SAMPLING SYSTEMS (TAC NOS.

MB7998 AND MB7999)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 212 to Facility Operating License No. NPF-14 and Amendment No. 187 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units I and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 3, 2003.

These amendments delete TS 5.5.3, "Post Accident Sampling,' and thereby eliminate the requirements to have and maintain the post-accident sampling systems for SSES, Units 1 and 2. The amendments also address related changes to TS 5.5.2, "Primary Coolant Sources Outside Containment."

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 212 to License No. NPF-14

2. Amendment No. 187 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 5, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENT RE: INTERMITTENT OPENING OF ISOLATED FLOW PATHS AND TIP ISOLATION (TAC NOS. MB6665 AND MB6666)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 213 to Facility Operating License No. NPF-14 and Amendment No. 188 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 31, 2002.

These amendments revise Technical Specifications (TSs) Section 3.3.6.1, "Primary.

Containment Isolation Instrumentation," to add an ACTIONS Note allowing intermittent opening, under administrative control, of penetration flow paths that are Isolated. Additionally,-these amendments revise TSs to breakout the traversing ncore probe system isolation as a separate Isolation Function with an associated Required Action to isolate the penetration within'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rather than immediately initiating a unit shutdown. As stated In your application, changes to the Bases for TS 3.3.6.1 will be addressed In accordance with TS 5.5.10, TS Bases Control Program."

A copy of our safety evaluation Is also enclosed. The Notice of Issuance will be included in the

,Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 213 to License No. NPF-14

2. Amendment No. 188 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 10, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS I AND 2 - ISSUANCE OF AMENDMENTS RE: EXTENDED OUTAGE TIME FOR OFFSITE POWER -

SINGLE OCCURRENCE (TAC NOS. MB9903 AND MB9904)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 214 to Facility Operating License No. NPF-14 and Amendment No. 189 to Facility Operating License No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated July 3, as supplemented by letters dated September 9 and 23, 2003.

The amendments change the Technical Specification (TS) to allow a one-time only change to TS 3.8.1, UAC [Altemating Current] Sources - Operating," Action A.3, by extending the required Completion Time for restoration of an inoperable offsite circuit from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included In the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 214 to License No. NPF-14

2. Amendment No. 189 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED RESPONSE TO GENERIC LETTER 94-02 "LONG-TERM STABILITY SOLUTION" (TAC NOS. MB900B AND MB9009)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has ssued the enclosed Amendment No. 215 to Facility Operating License No. NPF-14 and Amendment No. 190 to Facility Operating Ucense No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated May 6, as supplemented by letters dated August 12, and September 18, 2003.

The amendments delete Technical Specification (TS) 3.3.1.3, Oscillation Power Range Monitor (OPRM) Instrumentation," which has not yet been Implemented, and revise TS34.1, "Recirculation Loops Operating," to formally extend the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic Instability events. In addition, the amendments revise TS 3.4.1 to refer to the power flow map in the core operating limits report and Include a reference in TS 5.6.5. The requirements serves as an interim solution until plant-specific analyses is completed and the OPRM system and associated TSs are implemented.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included In the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 215 to License No. NPF-14

2. Amendment No. 190 to License No. NPF-22

3. Safety Evaluation cc w/encs: See next page

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6, 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.3 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.4.2 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.7.1 USE AND APPLICATION....................

1.1-1 Definitions 1.1-1 Logical Connectors 1.2-1 Completion Times 1.3-Frequency 1.4-1 SAFETY LIMITS (SLs).

2.0-1 SLs.................................................................................................1.....2.

1 SL Violatlons 2.0.1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.

3.04 REACTIVITY CONTROL SYSTEMS

.3.1-1 Shutdown Margin (SDM)

.3.11 Reactivity Anomalies 3.1-5 Control Rod OPEiRABILITY............................................................... 3.1-7 Control Rod Scram Times

.3.1-12 Control Rod Scram Accumulators 3.1-15 Rod Patterri.Control..............

3.1.18 Standby Uquid Control (SLC) System

.3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves..

3.1-25 POWER DISTRIBUTION LIMITS

.3.2-1 Average Planar Linear Heat Generation Rate (APLHGR).

3.2-1 Minimum Critical Power Ratio (MCPR).3.2-3 Linear Heat Generation Rate (LHGR).3.2-5 Average Power Range Monitor (APRM) Gain and Setpoints.

3.2-7 INSTRUMENTATION.............................................................................. 3.3-1 Reactor Protection System (RPS) Instrumentation.3.3-1 Source Range Mon itor (SRM) Instrumentation.3.3-10 Control Rod Block Instrumentation..

3.3-16 Feedwater - Main Turbine High Water Level Trip Instrumentation 3.3-21 Post Accident Monitoring (PAM) Instrumentation

.3.3-23 Remote Shutdown System...

3.3-27 End of Cycle Recirculation Pump Trip (EOC-RPT).

I nstrumnentation

.3.3-30 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentatlon 3.3-34 Emr&gericy Core Cooling System (ECOS) Instrumentation.

3.3.37 Reactor Core Isolation Cooling (CIC) System Instrumentation............................................................................ 3.3-48 Primary Containment Isolation Instrumentation 3.3-52 Secondary Containment Isolation Instrumentation.

3.3-63 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation........

... 3.3-67 I

(continued)

SUSQUEHANNA-UNIT 2 Amendment +Si- -+56-190 SUSQUEHANNA-UNIT 2 i

Amendment 1 5z, 1

5B 19

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS NOTES

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in trip.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable.

Functions 2.a, 2.d, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.d, 6.b, 7.a, and 7.b B.

One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with isolation capability.

capability not maintained.

(continued)

SUSQUEHANNA-UNIT 2 TS / 3.3-52 Amendment iR, 1&

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACTION C.t REQUIREMENTS VALUE

6.

Shutdown Cooling System Isolation

a.

Reactor Steam Dome 1.2.3 1

F SR 3.3.6.1.2 s108 psig Pressure - High SR 3.3.6.1.3 SR 3.3.6.1.5

b.

ReactorVesselWater 34,5 2()

J SR 3.3.6.1.1 2 11.5 Inches Level Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

c.

Manual Initatlon 3.4.5 1

G SR 3.3.6.1.5 NA

7.

Traversing Incore Probe Isolation

a.

ReactorVesselWater 1,2,3 2

G SR 3.3.6.1.1 2 11.5 Inches Level -

Low. Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

b.

Drywell Pressure-1.2,3 2

G SR 3.3.6.1.2 1.88 psIg High SR 3.3.6.1.4 SR 3.3.6.1.5 (c)

Only one trip system required In MODES 4 and 5 when RHR Shutdown Cooling System Integrity maintained.

SUSQUEHANNA - UNIT 2 TS / 3.3-62 Amendment Ix, 188

-- - -RecIrcalati i oop6 0oi~rg-3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be In operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified in the COLR.

OR One recirculation loop may be In operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified In the COLR, provided the following limits are applied when the associated LCO is applicable:

a.

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

b.

LCO 3.2.2, MINIMUM CRIICAL POWER RATIO (MCPIR),

single loop operation limits specified In the COLR;

c.

LCO 3.2.3, LINEAR HEAT GENERATION RATE' (LHGR),-

single loop operation limits specified In the COLR, and

d.

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

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

e.

Recirculation pump speed Is S 80%.

- ^ -

~

~~~~~~~No Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY:

MODES I and 2.

SUSQUEHANNA-UNIT 2 TS 3.4-1i Amendment<,

.10

RecircuatiorLoops Operating

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Region 1 of the Power Flow Map as specified In the COLR.

OR No recirculation loops operating while In MODE 1.

B.

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

Power Flow Map as specitied in the COLR.

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

OR Two or more LPRM upscale alarms activating and deactivating with a period 2 1 second and

< 5 seconds.

OR Sustained LPRM oscillations > 10 wicn 2 peak-to-peak with a period 21 second and

< seconds.

OR (continued)

-SUSQUEHANNA - UNIT 2 TS /3.4-2 ArnendmentX, 154, 1C)o

- RecirculationtLoops-Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

Less than 50% of required LPRM upscale alarms OPERABLE.

C.

Total core flow as a C.1 Initiate action to restore Immediately function of THERMAL total core flow as a POWER within function of THERMAL Region II of the Power POWER outside of Flow Map as specified Region II.

in the COLR.

D.

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

lower flow to be not in operation."

E.

No recirculation loops E.1 Be In MODE 3.

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

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

SUSQUEHANNA - UNIT 2 TS /3.4-3 Amendment X fi, 1g1

~--Recirculation Laops <3perating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 OTE D

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

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

a.

10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b.

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

SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ThERMAL POWER is outside of Region I and 11 of the Power Flow Map as specified In the COLR.

SR 3.4.1.3

-NO-TE-Only required to be met during single loop operations.

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

I I

SUSQUEHANNA - UNIT 2 TS / 34-4 Amendment<, Iv, ic'

3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK' M =

ffi Xl r4-SUSQUEHANNA - UNIT 2 TS /3.4-5 Amendment 1A{,

,190

.1

.. Main Turbine Bypass System 3.7.6 3.7 3.7.6 PLANT SYSTEMS Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR),' limits for an inoperable Main Turbine Bypass System, as specified n the COLR, are made applicable.

APPLICABILITY:

THERMAL POWER f 26% RTP.

ACTIONS CONDITON REQUIRED ACTION COMPLETION TIME

.. 1.

A. Main Turbine Bypass..

Systemn noperable.

AND Requirements of LCO 3.2.2 not met.

A.1 Satisfy the requirements of the LCO or restore Main Turbine Bypass System to OPERABLE status.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Required Action and B-1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completlon Time

<25% RTP.

not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cyrcle of each required main 31days turbine bypass valve.

I (continued)

SUSQUEHANNA - UNIT 2 TS 13.7-1 5 Amnendment HE1, 185

PPL Rev. 0 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION 1lME 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 discovery of no offsite available Inoperable when the power to one 4.16 kV redundant required feature(s)

ESS bus concurrent are Inoperable.

Wth Inoperability of redundant required feature(s).

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

AND 6 days from discovery of failure to meet LCO OR 10 days from a one-time outage for replacement of Startup Transformer Number 10 to be completed by December 31, 2003 (continued)

I SUSQUEHANNA - UNIT 2 TS 3.6-2 Amendment 15 1B

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 ODCM (continued) shall indicate the date (I.e., month and year) the change was mplemented.

Primary Coolant Sources Outside Containment 5.5.2 This program provides controls to minimie leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems Include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, Standby Gas Treatment, Scram Discharge, Post Accident Sampling (until such time as a modification eliminates the PASS penetration as a potential leakage path) and Containment Air Monitoring Systems. The program shall include the following:

I

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 montlhs.

The provisions of SR 3.0.2 are applicable.

Not Used Radioactive Effluent Controls Program 5.5.3 5.5.4 This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably (continued)

SUSQUEHANNA - UNIT 2 TS/5.0-8 Amendment. No.

451, ieh 187.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Test Program (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P (inches wg)

Flowrate (cfm)

Standby Gas Treatment System Control Room Emergency Outside Air Supply System

<13

<7.3 9,090 to 11,110 5,229 to 6,391 I

e. Demonstrate that the temperature differential in the air flow across the heating coils for each of the ESF system Is greater than or equal to the value specified below when tested In accordance with ASME N51 0-1 975:

ESF Ventilation System Delta T (F)

Flowrate (cfm)

Standby Gas Treatment System 17 9,090 to 11,110

f. Demonstrate that the heaters for each of the ESF system dissipate the value specified below when tested in accordance with ANSI N51 0-1 975:

ESF Ventilation System Control Room Emergency Outside Air Supply System Wattage (kW) 27 to 33 5.5.8 ExDlosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures".

The program shall include:

a. The limits for concentrations of hydrogen In the Main Condenser Offgas Treatment System and a (continued)

SUSQUEHANNA - UNIT 2 TS /5.0-14 Amendment 4-61, 186

Reporting Requirements Reporting Requ5rements 5.6 Reporting Requirements 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, Including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2.

The Minimum Critical Power Ratio for Specification 3.2.2;

3.

The Linear Heat Generation Rate for Specification 3.2.3; 4

The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and

5.

The Shutdown Margin for Specification 3.1.1.

6.

The stability related regions of the Power Flow Map for Specification 3.4.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt Is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFMTM) as described in the LEFM /

Topical Report and supplement referenced below.

When feedwater flow measurements from the LEFMTM system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (102% of 3441 MWt) remains the initial power level for the bounding licensing analysis.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment A 190

Reporting Requirements

-......--__. _-.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

11.

Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMAM' or LEFM CheckPlus' System," Engineering Report ER-1 60P.

12.

EMF-85-74(P)(A), URODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."

13.

EMF-21 58(P)(A), "Siemens Power Corporation Methodology for Bolling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2,0 Siemens Power Corporation.

14.

EMF-CC-074(P)(A), Volume 4, "BWR Stability Analysis: Assqssment of STAIF with Input from MICROBURN-B2."

c.

The core operating limits shall be determined such that all.applicabie limits (e.g.,

fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, Including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures In the last 25 demands, these failures and any nonvalid failures experienced by that EDG In that time period shall be reported within 30 days.

Reports on EDG failures shall Include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4.

5.6.7 PAM Report When a report Is required by Condition B or F of LCO 3.3.3.1, Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the noperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

SUSQUEHANNA - UNIT 2 TS / 5.0-23 A

dmen 1/9, 1

1rBv

p* aeon, UNITED STATES H i S

NUCLEAR REGULA"ORY COMMISSION WASHINGTON. D.C. 20555-01 July 30, 1999 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer PP&L, Inc.

2 North Ninth Street Allentown, PA 18101

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS.

MA2271 and MA2445)

Dear Mr. Byram:

The Commission has issued the enclosed Amendment No. 184 to Facility Operating License No. NPF-1 4 and Amendment No. 158 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your applications dated June 19, 1998, (Unit 1) and August 5, 1998, (Unit 2) as supplemented by letters dated November 23, 1998 (Units 1 and 2), and June 23, 1999.

These amendments Incorporate long-term power stability solution instrumentation into the, SSES Unit i and Unit 2 TS. The changes reflect the addition of a new TS Section 3.3.1.3i(

"Oscillation Power Range Monitoring Instrumentation," and revisions to TS Section 3.4.1, "Recirculation Loops Operating," to remove specifications related to the curreit!power stability.

specifications that are no longer required.

A copy of our safety evaluation Is also enclosed. Notice of Issuance will be included In the Commission's Biweekly Federal Register Notice.

Sincerely, Victor Nerses, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387/50-388

Enclosures:

1. Amendment No. 184 to Ucense No. NPF-14

2. Amendment No. 158 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 10, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: EXTENDED OUTAGE TIME FOR OFFSITE POWER -

SINGLE OCCURRENCE (TAC NOS. MB9903 AND MB9904)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 214 to Facility Operating License No. NPF-14 and Amendment No. 189 to Facility Operating License No.

'NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated July 3, as supplemented by letters dated September 9 and 23, 2003.

The amendments change the Technical Specification (TS) to allow a one-time only change to TS 3.8.1,,"AC [Alternating Current] Sources - Operating," Action A.3, by extending the required Completion Time for restoration of an Inoperable offsite circuit from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 214 to License No. NPF-14

2. Amendment No. 189 to License No. NPF-22

3. Safety Evaluation cc w/encls; See rext page

October 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED RESPONSE TO GENERIC LETTER 94-02 "LONG-TERM STABILITY SOLUTION" (TAC NOS. MB9008 AND MB9009)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has Issued the enclosed Amendment No. 215 to Facility Operating License No. NPF-14 and Amendment No. 190 to Facility Operating License No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated May 6, as supplemented by letters dated August 12, and September 18, 2003.

The amendments delete Technical Specification (TS) 3.3.1.3, Oscillation Power Range Monitor (OPRM) Instrumentation," which has not yet been implemented, and revise TS 4.1,

'Recirculation Loops Operating," to formally extend the currently implemented requirements, which define appropriately conservative restrictions to plant operation and operator-response to thermal hydraulic instability events. In addition, the amendments revise TS 3.4:1 to refer to the power flow map in the core operating limits report and Include a reference in TS 5.6.5. The requirements serves as an interim solution until plant-specific analyses is completed and the OPRM system and associated TSs are implemented.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 215 to License No. NPF-14

2. Amendment No. 190 to License No. NPF-22

3. Safety Evaluation cc wencs: See next page

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).............

2.0-1 2.1 SL s......................................................................................................2.0-1 2.2 SL Violations............

2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

.................. 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 Setpolnts.

3.2-7 3.3 INSTRUMENTATION...........................................

3.3-1 3.3.1.1 Reactor Protection.System (RPS) Instrumentation............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 3.3.2.1 Control Rod Block Instrumentation.

I.......

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) Instrurentation

......................... 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation...............

3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation.................

............. 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation.................................

3.-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 I I

Amendment-1-84, 215 SUSQUEHANNA - UNIT I i

Amendment, 25

Recirculating Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified In the COLR.

OR-One recirculation loop may be In operation provided the following limits are applied when the associated LCO is applicable with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified In the COLR.

a.

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

b.

LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR),

single loop operation limits specified In the COLR;

c.

LCO 32.3, LINEAR HEAT GENERATION RATE (LHGR),

single loop operation limits specified In the COLH, and

d.

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

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

e.

Recirculation pump speed Is 5 80%.

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

APPIUCABILiTY:

MODES I and 2.

SUSQUEHANNA -UNIT I TTS / 3.4-1 Amendmnt 13iB, 25

- RecirculatinLops Op ratlfrg -

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Region I of the Power Flow Map as specified in the COLR.

OR No recirculation loops operating while In MODE 1.

B.

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

Power Flow Map as specified In the COLR.

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

OR Two or more LPRM upscale alarms activating and deactivating with a period 1 second and 5 seconds.

OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period > 1 second and

<5 seconds.

(continued)

OR SUSQUEHANNA-UNIT I TS / 3.4-2 Amendment 8 i^,

15

Recirculating Loops erating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

Less than 50% of required LPRM upscale alarms OPERABLE.

C.

Total core flow as a C.1 Initiate action to restore Immediately function of THERMAL total core flow as a POWER within function of THERMAL Region II of the Power POWER outside of Flow Map as specified Region II.

In the COLR.

D.

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

lower flow to be not In operation."

E.

No recirculation loops E.1 Be In MODE 3.

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

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

-SUSQUEHANNA-UNIT I TS / 3.4-3 Amnendment 18 if, 2:L

Recirculating L-oops Operating- - -

3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 NOTE-Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are In operation.

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

a.

< 10 milllon Ibnm/h when operating at

< 75 million lbn-hr total core flow; and

b.

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

SR 3A.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER Is outside of Region I and II of the Power Flow Map as specified In the COLR.

SR 3.4.1.3 OTE-Only required to be met during single loop operations.

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

SUSQUEHANNA - UNIT 1 TS /3,.44 Amendment 1,8, 1., 215

f-lirt

&t.

t f~~IUfUl U~

i b~l 3.4.1

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

THIS PAGE INTENTIONALLY LEFT BLANK Vt? ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~p.

SUSQUEHANNA - UNIT 1 TS / 34.5 Amendment 1I; A,- X4 21.5

PPL Rev. 0 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 6 days from discovery of failure to meet LCO OR 10 days for a one-time outage for replacement of Startup Transformer Number 10 to be completed by December 31, 2003 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 noperability of required feature(s) are inoperable.

redundant required feature(s)

AND (continued)

I SUSQUEHANNA-UNIT 1 TS / 3.8-2 Amendment 17 14

PPL Rev. 0 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

B.3.1 Determine OPERABLE DGs are 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.7 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DGs.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to entering Condition B B.4 Restore required DG 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 C. Two offsite circuits C.1 Restore one offsite circuit to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable.

OPERABLE status.

D. One offslte circuit NOTE----

inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.7, Distribution AND Systems-Operating," when Condition D Is entered with no AC power source to any One required DG 4.16 kV ESS bus.

inoperable.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR D.2 Restore required DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

_____ _____ ____ __ __ _(continued)

SUSQUEHANNA - UNIT 1 TS /3.8-3 Amnendment 17l 214

PPL Rev. 0 AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more E.1 Restore at least three required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months required DGs DGs to OPERABLE status.

inoperable.

F. Required Action F.1 Be In MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Associated Completion Time of AND Condition A, B, C, D, or E not met.

F.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. One or more offsite G.A Enter LCO 3.0.3.

Immediately circuits and two or more required DGs inoperable.

OR One required DG and two offsite circuits inoperable.

SURVEILLANCE REQUIREMENTS Four DGs are required and a DG is only considered OPERABLE when the DG Is aligned to the Class 1 E distribution system. DG Surveillance Requirements have been modified to Integrate the necessary testing to demonstrate the availability of DG E and ensure its OPERABILITY when substituted for any other DG. If the DG Surveillance Requirements, as modified by the associated Notes, are met and performed, DG E can be considered available and OPERABLE when substituted for any other DG after performance of SR 3.8.1.3 and SR 3.8.1.7.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power 7 days availability for each offsite circuit.

(continued)

SUSQUEHANNA - UNIT 1 TS /3.8-4 Amendment 17Y/ 214

-~~

~

~ ~

~~

~ ~~-~

~~-~

Reportirng ReqUlrgmet-s~

5.6 5.6 Reporting Requirements (continued) 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the I of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented In the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Spedcification 3.2.1;

2. The Minimum Critical Power Ratio for Specification 3.2.2;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Average Power Range Monitor (APRM) Gain and Setpolnts for Specification 3.2.4; and

5. The Shutdown Margin for Specification 3.1.1.

6. The stability tlated regions of.the Power Flow Map for SpecIfication 3.4.1.

I

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an Initial assumed power level of 102 percent of rated power Is specified In a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt Is 100.6% of the rated thermal power level of 3489 MWt The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) Is provided by the Leading Edge Flow Meter (LEFMVTU) as described In the LEFM/Tu Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMV'nl system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt.

(continued)

Amendment 4,94-215 SUSQUEHANNA-UNIT I TS 5.0-21

----------------~----------.-Reporting Requirements-5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

9. ANF-91-048(P)(A), 'Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model.

10. XN-NF-80-1 9(P)(A), Exxon Nuclear Methodology for Boiling Water Reactors.

11. XN-NF-79-71 (P)(A), 'Exxon Nuclear PlantTransient Methodology for Boiling Water Reactors.'

12. EMF-1997(P)(A), ANFB-10 Critical Power Correlation.'

13. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMVTAS System," Engineering Report SOP.

14. Caldon, Inc., Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMIu or LEFM CheckPlusu System,', Engineering Report ER-160P.

15. EMF-85-74(P), RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model.'

16. EMF-CC-074(P)(A), Volume 4, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2."

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic lmits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met

d. The COLR, including any midcycle revisions or supplements, shall be provided upon Issuance for each reload cycle to the NRC.

(continued)

SUSQUEHANNA - UNIT I TS / 5.0-23 Arpend ent8

,6, yB9, 1,4; z9215

UNITED STATES t o NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205-0001 3uly 30, 1999 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer PP&L, Inc.

2 North Ninth Street Allentown, PA 18101

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS.

MA2271 and MA2445)

Dear Mr. Byram:

The Commission has Issued the enclosed Amendment No. 184 to Facility Operating License No. NPF-1 4 and Amendment No. 158 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your applications dated June 19, 1998, (Unit 1) and August 5, 1998, (Unit 2) as supplemented by letters dated November 23, 1998 (Units 1 and 2), and June 23, 1999.

These amendments Incorporate long-term power stability solution instrumentation into the

'SSES Unit 1 and Unit 2 TS. The changes reflect the addition of a new TS S-t86n3.3.1.3, "Oscillation Power Range Monitoring Instrumentation," and revisions to TS Secti6n 3:4.i, "Recirculation Loops Operating,' to remove specifications related to the current powbr stability specifications that are no longer required.

a.

A copy of our safety evaluation is also enclosed. Notice of Issuance will be included In the Commission's Biweekly Federal Register Notice.

Sincerely, Victor Nerses, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387/50-388

Enclosures:

1. Amendment No. 184 to Ucense No. NPF-14

2. Amendment No. 158 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 3, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: POST-ACCIDENT SAMPLING SYSTEMS (TAC NOS.

MB7998 AND MB7999)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 212 to Facility Operating License No. NPF-14 and Amendment No. 187 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 3, 2003.

These amendments delete TS 5.5.3, Post Accident Sampling," and thereby eliminate the requirements to have and maintain the post-accident sampling systems for SSES; Units 1 and 2. The amendments also address related changes to TS 5.5.2, "Primary Coolant Sources Outside Containment."

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRAI Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 212 to License No. NPF-14

2. Amendment No. 187 to License No. NPF-22

3. Safety Evaluation cc w/encs: See next page

October 10, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENTS RE: EXTENDED OUTAGE TIME FOR OFFSITE POWER -

SINGLE OCCURRENCE (TAC NOS. MB9903 AND MB9904)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 214 to Facility Operating License No. NPF-14 and Amendment No. 189 to Facility Operating License No.

'NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated July 3, as supplemented by letters dated September 9 and 23, 2003.

The amendments change the Technical Specification (TS) to allow a one-time only change to TS,3.8.1, -AC [Alternating Current] Sources - Operating," Action A.3, by extending the required Completion Time for restoration of an inoperable offsite circuit from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 214 to License No. NPF-14

2. Amendment No. 189 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

October 29, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED RESPONSE TO GENERIC LETTER 94-02 "LONG-TERM STABILITY SOLUTION" (TAC NOS. MB9008 AND MB9009)

Dear Mr. Shriver:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 215 to Facility Operating License No. NPF-14 and Amendment No. 190 to Facility Operating Ucense No.

NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments are in response to your application dated May 6, as supplemented by letters dated August 12, and September 18, 2003.

The amendments delete Technical Specification (TS) 3.3.1.3, "Oscillation Power-Range Monitor (OPRM) Instrumentation," which has not yet been implemented, and revise TS-3.4:1, "Recirculation Loops Operating," to formally extend the currently implemented requirements, -

which define appropriately conservative restrictions to plant operation and operator response to thermal hydraulic instability events. In addition, the amendments revise TS 3.4.1 to refer to the power flow map in the core operating limits report and Include a reference in TS 5.6.5. The requirements serves as an interim solution until plant-specific analyses is completed and the OPRM system and associated TSs are implemented.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 215 to License No. NPF-14

2. Amendment No. 190 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6X 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.3 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.1 3.3.3.2 3.3.3.1 3.3.4.2 3.3.4.1 3.3.5.2 3.3.5.1 3.3.6.2 3.3.6.1 3.3.7.1 USE AND APPLICATION................

1.1-1 Definitions.

1.1-1 Logical Connectors 1.2-1 Completion Times 1.3-1 Frequency...........

1.4-1 SAFETY LIMITS (SLs)..................................................2..............................12.

1 SLs......................................................................................................2.01 SL Vlolations 2.0-1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY............................ 3.0-4 REACTIVITY CONTROL SYSTEMS 3.1-1 Shutdown Margin (SDM) 3.1-1 Reactivity Anomalies......................

3.1-5 Control Rod OPERABILI1Y....................

3.1-7 Control Rod Scram Times......

3.1-12 Control Rod Scram Accumulators

....... 3.1-15 Rod Pattem.Cortrol..........

3.1 -1 Standby Liquid Control (SLC) System

.............................. 3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves................... 3.1-25 POWER DISTRIBUTION LIMITS.

......................................... 3.2-1 Average Planar LUnear Heat Generation Rate (APLHGR) 3.2-1 Minimum Critical Power Ratio (MCPR)..........................................

32-3 Linear Heat Generation Rate (LHGR)..........................................

3.2-5 Average Power Range Monitor (APRM) Gain and Setpolnts.............

3.2-7 INSTRUMENTATION...

3.3-1 Reactor Protection System (RPS) Instrumentation.

33-1 Source Range Monitor (SRM) nstrumentation.................................. 3.3-10 Control Rod Block nstrumentation...................................................3.3-16 Feedwater - Main Turbine High Water Level Trip Instrumentatlon......................................

.. 3.3-21 Post Accident Monitoring (PAM) Instrumentation 3.3-23 Remote Shutdown System 3.3-27 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation......

............ 3.3-30 Anticipated Translent Without Scram Recirculation Pump Trip (ATWS-RPT) nstrum'entation 3.3-34 Emrgency Core Cooling System (ECCS) Instrumentation.............. 3.3-37 Reactor Core Isolation Cooling (RCIC) System Instrumentatlon 3.3-48 Primary Containment Isolation Instrumentation

........ 3.3-52 Secondary Containment Isolation Instrumentation

..................... 3.3-63 Control Room Emergency Outside Air Supply (CREOAS)

'System Instrumentation :

3.3-67 I

(continued)

SUSQUEHANNA - UNIT 2 I

Amendment *1-; 5&-1g)

SUSQUEHANNA - UNIT 2 I

Ame ment 1i-, 5 I

-- -.~

~Reirdoiation Loups Opuefatitng 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be In operation with a THERMAL POWER/core flow condition outside of Regions I and II of the Power Flow Map as specified in the COLR.

OR One recirculation loop may be In operation with a THERMAL POWER/core flow condition outside of Regions I and 11 of the Power Flow Map as specified In the COLR, provided the following limits are applied when the associated LCO Is applicable:

a.

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

b.

LCO 3.2.2, MINIMUM CRItICAL POWER RATIO (MCPR),

single loop operation limits specified In the COLR;

c.

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

single loop operation limits specified In the COLR, and

d.

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

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

e.

Recirculation pump speed s < 80%.'

~~

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

APPLICABILITY:

MODES I and 2.

SUSQUEHANNA - UNIT 2.

. TS/ 3.4-1 Arnendent4., Rio.

R ec-rcuiat 1-6Loops Operating

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Region I of the Power Flow Map as specified In the COLR.

OFF No recirculation loops operating while In MODE 1.

B.

NOTE--

B.1 Place the reactor mode Immediately Only applicable when switch in the shutdown In Region 11 of the position.

Power Flow Map as specified In the COLR.

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

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

< 5 seconds.

OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period 1 second and

5 seconds.

(continued)

OR SUSQUEHANNA - UNIT 2 TS / 3.4-2 Arrendmente 15R, 10

- RecirculationLoopsfOperating -

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

Less than 50% of required LPRM Lpscale alarms OPERABLE.

C.

Total core flow as a C.1 Initiate action to restore Immediately function of THERMAL total core flow as a POWER within function of THERMAL Region II of the Power POWER outside of Flow Map as specified Region II.

In the COLR.

D.

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

lower flow to be not In operation.'

E.

No recirculation loops E.1 Be In MODE 3.

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

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

SUSQUEHANNA - UNIT 2 TS /3.4-3

AmendmeniX +fi191)

-Recirculation tLops-Operating-3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

+

SR 3.4.1.1

--- No t-Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are In operation.

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

a.

< 10 million Ibm/hr when operating at c 75 million Ibm/hr total core flow; and

b.

5 million bm/hr when operating at

, 75 million Ibm/hr total core flow.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months THERMAL POWER Is outside of Region I and 11 of the Power Flow Map as specified In the COLR.

SR 3.4.1.3

-NOTE---

Only required to be met during single loop operations.

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

I I

SUSQUEHANNA - UNIT 2 TS / 34-4 Amendment<,

, 1)

3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK'

G I

r

.,T aa ir

.II I

R

, 3 3aff.;'M SUSQUEHANNA - UNIT 2 TS / 3.4-5 Amendment 11. X l9o

PPL Rev. 0 AC Sources - Operating 3.6.1 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 discovery of no offsite available Inoperable when the power to one 4.16 kW 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 statds.

AND 6 days from discovery of failure to meet LCO OR 10 days from a one-time outage for replacement of Startup Transformer Number 10 to be completed by December 31, 2003 (continued)

I I

SUSQUEHANNA-UNIT 2 TS / 31-2 Amendment 1 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 ODCM (continued) shall indicate the date (i.e., month and year) the change was implemented.

Primary Coolant Sources Outside Containment 5.5.2 This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems Include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, Standby Gas Treatment, Scram Discharge, Post Accident Sampling (until such time as a modification eliminates the PASS penetration as a potential leakage path) and Containment Air Monitoring Systems. The program shall Include the following:

I

a. Preventive maintenance and periodic visual Inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 months.

The provisions of SR 3.0.2 are applicable.

Not Used Radioactive Effluent Controls Program 5.5.3 5.5.4 This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably (continued)

SUSQUEHANNA - UNIT 2 TS I 5.0-8 Amendment. No.

45+,, 187.

Reporting Requirements 5.6 Reporting Requirements 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, Including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2.

The Minimum Critical Power Ratio for Specification 3.2.2;

3.

The Linear Heat Generation Rate for Specification 3.2.3; 4

The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and

5.

The Shutdown Margin for Specification 3.1.1.

6.

The stability related regions of the Power Flow Map for Specification 3.4.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an Initial assumed power level of 102 percent of rated power Is specified In a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt Is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as Input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFMA'M) as described In the LEFM /r Topical Report and supplement referenced below.

When feedwater flow measurements from the LEFMTM system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (102% of 3441 MWt) remains the initial power level for the bounding licensing analysis.

(continued)

SUSQUEHANNA - UNIT 2 TS I 5.0-21 Amendment 9 19)

Reporting Requirements 6.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

11.

Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM/'m or LEFM CheckPlustM System," Engineering Report ER-1 60P.

12.

EMF-85-74(P)(A), "RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."

13.

EMF-2158(P)(A), uSiemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2,"

Siemens Power Corporation.

14.

EMF-CC-074(P)(A), Volume 4, "BWR Stability Analysis: Assqssment of STAIF with Input from MICROBURN-B2."

l

c.

The core operating limits shall be determined such that all applicable limits (e.g.,

fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, Including any midcycle revisions or supplements, shall be provided upon Issuance for each reload cycle to the NRC.

5.6.6 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures In the last 25 demands, these failures and any nonvalid failures experienced by that EDG In that time period shall be reported within 30 days.

Reports on EDG failures shall Include the Information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4.

5.6.7 PAM Report When a report Is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the noperability, and the plans and schedule for restoring' the Instrumentation channels of the Function to OPERABLE status.

SUSQUEHANNA - UNIT 2 TS /5.0-23 Ampndment1i 9, 1q 1U

v t e Letter Sequence Other
TAC:MB6671, (Open) TAC:MB6672, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML031490374, ML031500494, ML040330401
MONTHYEAR2003-05-29 [Table View]

ML040330401

Text

SUBJECT:

Dear Mr. Shriver:

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Dear Mr. Shriver:

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Dear Mr. Shriver:

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Dear Mr. Byram:

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Dear Mr. Shriver:

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Dear Mr. Shriver:

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Dear Mr. Shriver:

Enclosures:

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