ML033090403

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Tech Spec Pages for Amendments 215 & 190 Revised Response to Generic Letter 94-02 Long-Term Stability Solution
ML033090403
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 10/29/2003
From:
NRC/NRR/DLPM
To:
References
GL-94-002, TAC MB9008, TAC MB9009
Download: ML033090403 (16)
v • d • e


Text

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 Setpoints ............. 3.2-7 3.3 INSTRUMENTATION ............................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.2.1 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) Instrumrentation ..................................... 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)

Amendment-1-84, 215 SUSQUEHANNA - UNIT 1

- 1 i Amendmentl-e4,-215

-R-c-ircu O perating Ftn-g Coops 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 11of the Power Flow Map as specified in the COLR.

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

a. LCO 3.2.1, AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR),* single loop operation limits specified Inthe COLR;
b. LCO 3.2.2, 'MINIMUM CRITICAL POWER RATIO (MCPR),I single loop operation limits specified Inthe COLR;
c. LCO 3.2.3, LINEAR HEAT GENERATION RATE (LHGR),'

single loop operation limits specified Inthe 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< 80%.

~~~~~~~~~~Notea_

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

APPUCABILITY: MODES 1 and 2.

SUSQUEHANNA - UNIT I TS / 3.4-1 Amendment 1X8 IB4, 215

- --- "' -- - -. - ' -. "-- ----- -Recircuiatlng-toops-OpiE~rathfg -

3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Total core flow as a A.: 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.A 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 > 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating and deactivating with a period 21 second and

< 5 seconds.

OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period 2 1 second and S 5 seconds.

(continued)

OR SUSQUEHANNA - UNIT 1 TS / 3.4-2 Amendment 1/8 +/-F.f, 215

Recirculating Loops 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 IIof 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> mismatch not within recirculation loop with limits. lower flow to be unot in operation."

E. No recirculation loops E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> In operation while In -

MODE 2.

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

SUSQUEHANNA - UNIT I TS /3.4-3 Amendment 1/8 19A, 215

-.-- -- -Recirculating Loops Operating- - --

3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 --- ------- NOTE----

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

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

a. S 10 million Ibrnhr when operating at

< 75 million Ibm/hr total core flow; and

b.
  • 5 million IbmJhr when operating at 2 75 million Ibm/hr total core flow.

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

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

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

SUSQUEHANNA - UNIT 1 TS /3.4-4 Amendment g 1 8, 1*,, 25

~ Rd-ircuflatrgtopWOperating 3.4.1

_______ V~~~~~~~~74¶fl~~~~~Yt.

Wrtr~~~~~~~.1tvc rf~~~~.

~ptP4~'.r ~ _ ' ~ -- ii35.-t-MA

_*______ *+/-E wz~+/-i&

THIS PAGE INTENTIONALLY LEFT BLANK

"'1a '_~~gg a- 5~~g1&% -- t.g- f4 .

-, 27'~~~~~~~~. k ~ Z SUSQUEHANNA - UNIT 1 TS /3.4-5 Amendment 1761, 1,X4 215

-. - - ----- - - -~ Reporting Re-qurrenients--- -

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 le 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 Inthe 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 Unear 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 telated regions of.the Power Flow Map for Specification 3.4.1. l
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 Inthe LEFM&/Tu Topical Report and supplement referenced below. When feedwater flow measurements from the LEFM/Tu 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 4iS +94-215 SUSQUEHANNA - UNIT 1 TS 1 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.

1 1. XN-NF-79-71 (P)(A), Exxon Nuclear Plant Transient 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 LEFMVTu System," Engineering Report - OP.
14. Caldon, Inc., "Supplement to Topical Report ER-SOP: Basis for a Power Uprate with the LEFMVTu or LEFM CheckPlusTu System,', Engineering Report ER-I 60P.
15. EMF-85-74(P), ERODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model.'

STAIF with Input from MICROBURN-B2.N

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 mldcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

SUSQUEHANNA - UNIT I TS / 5.0-23 Amend ent8 1A6, 9,1 4, 215

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............................................................................................ .4-1 2.0 SAFETY LIMITS (SLs) ............ 2.0-1 2.1 SLs.................................................................................................0.....2. 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 OPERABILTY L ............ 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 Pattgrn.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 Unear Heat Generation Rate (APLHGR) .................. 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) ........................................... 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ........................................... 3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints ............. 3.2-7 3.3 INSTRUMENTATION ........................................... 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.2.1 Control Rod Block Instrumentation....................................................3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation ........... 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ................... 3.3-23 3.3.3.2 Remote Shutdown System . . ............................3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation.......................................................................... 3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation . . ................... 3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .............. 3.3-37 3.3.5.2 Reactor Core Isolation Cooling (ROIC) 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)

Amendment 459-; -i9O SUSQUEHANNA - UNIT 22

- i Amendment i 58 19(

-- -. - -- - ~~~~~~~~~~Recircolation tdops Operatitg ~~ ~

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 11of 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 11of the Power Flow Map as specified Inthe 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),3 single loop operation limits specified Inthe COLR;
c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),'

single loop operation limits specified Inthe 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%.

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

APPLICABILITY: MODES I and 2.

SUSQUEHANNA - UNIT 2 TS / 3.4-1 Amendrnentel---,,R, icm

Recircuiatro-n LOops Operating

  • 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Total core flow as a A.1 Place reactor mode Immediately function of THERMAL switch Inthe shutdown POWER within position.

Region I of the Power Flow Map as specrfied 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 Inthe 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 > 10% of RTP peak-to-peak.

OR Two or more LPRM upscale alarms activating and deactivating with a period 21 second and

  • 5 seconds.

OR Sustained LPRM oscillations > 10 w/cm2 peak-to-peak with a period 21 second and

  • 5 seconds.

OR (continued)

SUSQUEHANNA - UNIT 2 TS /3.4-2 Arriendmentie, 1-54, 1C)o

. -Recirculation-Loops 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> mismatch not within recirculation loop with limits, lower flow to be "not In operation."

E. No recirculation loops E.1 Be InMODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> In operation while in MODE 2.

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

SUSQUEHANNA - UNIT 2 TS /3.4-3 ArriendrrientX, +-%, 190

-Reclrculaion taops-0perating------

3.4.1 SURVEILLANCE REQUIREMENTS . ___________________.

SURVEILLANCE FREQUENCY SR 3.4.1.1 ----- NOTE---------

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

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

a. 5 10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b. s 5 million ibrn/hr when operating at 275 million Ibm/hr total core flow.

SR 3.4.1.2 Verify total core flow as a function of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> THERMAL POWER is outside of Region I and 11of the Power Flow Map as specified In the COLR. ,1 SR 3.4.1.3 --- NOTE Only required to be met during single loop operations.

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

I SUSQUEHANNA - UNIT 2 TS /3.4-4 Amendmentj e, rN, IC, 0

eRecircU1~Ir6oWL

- - - R perang --

3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK ar kw __- flt.4fi'I' SUSQUEHANNA - UNIT 2 TS /3.4-5 Amendment lx{, X ,190o

_____ ______ _-___* 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 (LEFMATM) as described Inthe LEFMVI 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 MWt (102% of 3441 MWt) remains the initial power level for the bounding licensing analysis.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 9 19J

Reporting Requirements

__---_-5.6 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 LEFMVIm or LEFM CheckPlusm System," Engineering Report ER-i 60P.
12. EMF-85-74(P)(A), "RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."
13. EMF-21 58(P)(A), 'Siemens 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."

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 midoycle 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 3.3.3.13 '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 Inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

SUSQUEHANNA - UNIT 2 TS / 5.0-23 Ampndment 1 , 1l9 1R~l

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