ML060650319

Issuance of Amendment Power Range Neutron Monitor System Digital Upgrade - Technical Specification 3.3 Instrumentation - 5.6 Reporting Requirements

ML060650319
Person / Time
Site:	Susquehanna
Issue date:	03/03/2006
From:	Richard Guzman Plant Licensing Branch III-2
To:	Mckinney B Susquehanna
References
TAC MC7486, TAC MC7487
Download: ML060650319 (28)

Text

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

---

NOTI =-- ------- - - -------------------------------------------- ---

Separate Condition entry is allowed for each chan CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hcurs channels inoperable.

OR A.2 ------------ NOTE----- --- - -- 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip B. --------NOTE--------------- B.1 Place channel in one trip 6 hou-s Not applicable for system in trip.

Functions 2.a, 2.b, 2.c, OR 2.d, or 2.f.

-- B.2 Place one trip system in trip 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> One or more Functions with one or more required channels inoperable in both trip systems.

C. One or more Functions C.1 Restore RPS trip capability. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with RPS trip capability not maintained.

(continued)

SUSQUEHANNA - UNIT 1 TS /3.3-1 Amendment 17,8, 230

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 ACTIONS (continued) _

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition referenced in Immediately associated Completion Table 3.3.1.1-1 for the channels.

Time of Condition A, B, or C not met.

E. As required by Required E.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action D.1 and < 30% RTP.

referenced in Table 3.3.1.1-1.

F. As required by Required F.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action D.1 and referenced in Table3.3.1.1-1.

G. As required by Required G.1 Be in MODE 3. 12 hoirs Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by Required H.1 Initiate action to fully insert all Immediately Action D.1 and insertable control rods in core cells referenced in containing one or more fuel Table 3.3.1.1-1. assemnblies.

I. As required by Required 1.1 Initiale alternate method to detect 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action D.1 and and suppress thermal hydraulic referenced in instability oscillations.

Table 3.3.1.1-1 .

AND 1.2 Restore required channels to 120 days OPERABLE.

J. Required Action and J.1 Reduce THERMAL POWER to 4 hourS associated Completion <25% RTP.

Time of Condition I not met.

SUSQUEHANNA - UNIT 1 TS /3.3-2 Amendment 1fi, 2 30

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS k firsr-

---

- -- ----------- - ------------- - - -------------------- flu,. J, I r-n ---- - - ------------ - --------- - --- - ----- - ----------- - -

1. Refer to Table 3.3.1.1-ito determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.1.2 Perform CHANNEL CHECK 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> SR 3.3.1.1.3 ---------------------------------- NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 2 25% RTP.

Verify the absolute difference between the average 7 days power range monitor (APRM) channels and the calculated power is <2% RTP plus any gain adjustment required by LCO 3.2.4, "Average Power Range Monitor (APRM) Setpoints" while operating at 2 25% RTP.

SR 3.3.1.1.4 --------------------------------- NOTE------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 (Jays (continued)

SUSQUEHANNA - UNIT 1 TS / 3.3-3 Amendment 1A, 230

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.11 --------- - ------------ ----- I',, tt- ____

1. Neutron detectors are excluded.

2. For Function 1.a, not required to be I performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL CALIBRATION. 134 days

• 1--

SR 3.3.1.1.12 -------------------------- NOTES------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST 184 days SR 3.3.1.1.13 Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months I SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and Turbine 24 months Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 30% RTP.

(continued)

SUSQUEHANNA- UNIT 1 TS /3.3-5 Amendment 1AO, 230

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.17 ------------- NOTES-----------

1. Neutron detectors are excluded.

2. For Function 5 "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency

3. For Function 2.e, "n" equals 8 channels for the purpose of determining the STAGGERED TEST BASIS Frequency. Testing of APRM and OPRM outputs shall alternate.

Verify the RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS SR 3.3.1.1.18 ---------------- NOTES-----------------------------

1. Neutron detectors are excluded.

2. For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION 24 months SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM Simulated 24 months Thermal Power is 2 30% and recirculation drive flow is < value equivalent to the core flow value defined in the COLR.

SR 3.3.1.1.20 Adjust recirculation drive flow to conform to reactor 24 months core flow.

SUSQUEHANNA - UNIT 1 TS /3.3-6 Amendment 01, 230

PPL Rev. 2 RPS Instrumentation 3.3.1.1 Tabla 3.3.1.1-1 (page 1 of 3)

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

1. Intermediate Range Monitors

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

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

2. Average Power Range Monitors

a. Neutron 2 G SR 3.3.1.1.2 S20% RTP Flux-High SR 3.3.1.1.7 (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18

b. Simulated 1 3(K, F SR 3.3.1.1.2 < 0.58 W Thermal SR 3.3.1.1.3 + 62% RTP(b) and Power-High SR 3.3.1.1.8 s 115.5% RTP SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.20 I (continued)

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

(b) 0.58(W-AW) + 62% RTP when reset for single loop operation per LCO 3.4.1, 'Recirculation Loops Ope ating.'

For single loop operation the value of AW = 5%/l/0.58. For two loop operation, the value of AW = 0. I (C) Each APRM channel provides inputs to both trip systems.

SUSQUEHANNA - UNIT 1 TSI/3.3-7 Amendment 17Z8,224 230

PPL Rev. 2 RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

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

2. Average Power Range Monitors (continued)

AC) F SR 3.3.1.1.2 S 120% RTP

c. Neutron 1 Flux-High SR 3.3.1.1.3 I SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18 I

d. Inop 1,2 G SR 3.3.1.1.12 NA I

e. 2-Out-Of4 1,2 2 G SR 3.3.1.1.2 NA Voter SR 3.3.1.1.12 SR 3.3.1.1.15 SR 3.3.1.1.17 225% RTP 3 (c) Cd)

f. OPRM Trip I SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.19 SR 3.3.1.1.20

3. Reactor Vessel 1,2 G SR 3.3.1.1.9 S 1093 psig Steam Dome SR 3.3.1.1.10 Pressure-High SR 3.3.1.1.15

4. Reactor Vessel 1,2 G SR 3.3.1.1.1 2 11.5 inches Water Level-Low, SR 3.3.1.1.9 Level 3 SR 3.3.1.1.10 SR 3.3.1.1.15

5. Main Steam 1 Cl F SR 3.3.1.1.9 S 11% closed Isolation Valve- SR 3.3.1.1.13 Closure SR 3.3.1.1.15 SR 3.3.1.1.17

6. Drywell Pressure- 1,2 G SR 3.3.1.1.9 S 1.88 psig High SR 3.3.1.1.10 SR 3.3.1.1.15 (continued)

(c) Each APRM channel provides inputs to both trip systems.

(d)

See COLR for OPRM period based detection algorithm (PBDA) setpoint limits. I SUSQUEHANNA - UNIT 1 TS /3.3-8 Arnendment 1Kg 23 0

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

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

7. Scram Discharge Volume Water Level-High

a. Level 1,2 2 G SR 3.3.1.1.9 S 66 gallons Transmitter SR 3.3.1.1.13 SR 3.3.1.1.15 5(a) .2 H SR 3.3.1.1.9 S 66 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

b. Float Switch 1,2 G SR 3.3.1.1.9 S 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15 5(a)

H SR 3.3.1.1.9 s 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

8. Turbine Stop Ž 30% RTP 4. E SR 3.3.1.1.9 S7% closed Valve-Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

9. Turbine Control 2 30% RTP E SR 3.3.1.1.9 > 460 psig Valve Fast Closure. SR 3.3.1.1.13 Trip Oil Pressure- SR 3.3.1.1.15 Low SR 3.3.1.1.16 SR 3.3.1.1.17 10 Reactor Mode 1,2 2 G SR 3.3.1.1.14 NA I Switch- Shutdown SR 3.3.1.1.15 Position 5 (a) 2 H SR 3.3.1.1.14 NA I SR 3.3.1.1.15

11. Manual Scram 1,2 2 G SR 3.3.1.1.5 NA SR 3.3.1.1.15 5(al 2 H SR 3.3.1.1.5 NA SR 3.3.1.1.15 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

SUSQUEHANNA - UNIT 1 TS /3.3-9 Amendment 174,230

PPL Rev. 1 Control Rod Bloc.k Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

---

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

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 ----------------------------------- NOTE-----------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at 5 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------------------------------------ NOTE-------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 ------------------------------------- NOTE-------------------------------

Neutron detectors are excluded.

Verify the RBM Trip Functions are not bypassed when 24 months THERMAL POWER is Ž 30% RTP.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL POWER 24 months is < 10% RTP.

(continued)

SUSQUEHANNA - UNIT 1 TS /3.3-18 Amendment IX, 230

PPL Rev. 1 Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE Rod Block Monitor

a. Low Power 1 (a) 2 SR 3.3.2.1.1 5 0.58W+55%(b)

Range- SR 3.3.2.1.4 Upscale SR 3.3.2.1.7

b. Inop 1(a) 2 SR 3.3.2.1.1 NA SR 3.3.2.1.4

c. Downscale 1 (a) 2 SR 3.3.2.1.1 Ž3/125 divisions of SR 3.3.2.1.4 full scale SR 3.3.2.1.7

2. Rod Worth 1(c), 2 (c) 1 SR 3.3.2.1.2 NA Minimizer SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3. Reactor Mode (d) 2 SR 3.3.2.1.6 NA Switch-Shutdown Position (a) When THERMAL POWER is 2 30% RPT (b) 0.58(W-AW) + 55% RTP when reset for single-loop operation per LCO 3.4.1. Recirculation Loops Operating."

For single-loop operation, the value of AW = 5%/0.!8. For two-loop operation, the value of AW = 0. I (c) With THERMAL POWER S 10% RTP.

(d) Reactor mode switch in the shutdown position.

SUSQUEHANNA - UNIT 1 TS I 3.3-20 Amendment 1X7, 2 3 0

PPL Rev. 3 Recirculating Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RUOS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

OR One recirculation loop may be in operation 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 locip 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 Simulated Thermal I Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

e. Recirculation pump speed is

• 80%.

---

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

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <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: M(DIDES 1 and 2.

SUSQUEHANNA - UNIT 1 TS / 3.4-1 A endment V?8, Z4, 2/5, 2 4, 230

PPL Rev. 1 SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the stertup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a, 2.d, and 2.e of Table 3.3.1. 1-1; I

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence.

OR

2. Conformance to the approved control rod sequence for 1he SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals that are not in conformance with the BPWS shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CFD charging water header pressure Ž 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

SUSQUEHANNA - UNIT 1 TS /3.10-20 Amnendment t.7-, 23 0

PPL Rev. 1 SDM Test - Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------------NOTE------------- --------------- NOTE---------------

Separate Condition entry Rod wcrth minimizer may be is allowed for each control bypassed as allowed by LCO rod. 3.3.2.1, "Control Rod Block

---

Instrumentation," if required, One or more control rods to allow insertion of not coupled to its inoperable control rod and associated CRD. continued operation.

A.1 Fully insert inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> control rod.

AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.2 Disarm the associated CRD.

B. One or more of the above B.1 Place the reactor mode Immediately requirements not met for switch in the shutdown reasons other than or refuel position.

Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for LCO According to the applicable 3.3.1.1, Functions 2.a, 2.d, and 2.e of SRs Table 3.3.1.1-1.

(continued)

SUSQUEHANNA - UNIT 1 'TS / 3.10-21 Amendment tV8, 230

PPL Rev. 4 Reporting Requirements 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 l5e 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;

5. The Shutdown Margin for Specification 3.1.1; and

6. Oscillation Power Range Monitor (OPRM) Trip Setpoints for Specification 3.3.1.1.

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 (LEFMV Tm) as described in the LEFMV TM Topical Report and supplement referenced below. When feedwater flow measurements from the LEFM/TM 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)

SUSQUEHANNA - UNIT 1 TS / 5.0-21 Amendment 18Z6, 194, 24-5, 24-7, 230,

PPL Rev. 2 RFS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1 -1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

_________________-----------------------------------------MtI t- - --- --- -- -_--- --- -- ---_. -- --- -- _-- --

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> channels inoperable.

OR A.2 ------------------ NOTE---------------- 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip.

B. ---------- NOTE------------ B.1 Place channel in one trip system 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Not applicable for in trip.

Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR One or more Functions B.2 Place one trip system in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with one or more required channels inoperable in both trip systems.

C. One or more Functions C.1 Restore RPS trip capability. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with RPS trip capability not maintained.

(continued)

SUSQUEHANNA - UNIT 2 TSq; / 3.3-1 Amendment l51, 20 7

PPL Rev. 2 RFPS Instrumentation 3.3.1.1 ACTIONS (continued) _

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition referenced Immediately associated in Table 3.3.1.1-1 for the Completion Time of channels.

Condition A, B, or C not met.

E. As required by E.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Action DA < 30% RTP.

and referenced in Table 3.3.1.1-1.

F. As required by F.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Required Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by G.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 /> Required Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by H.1 Initiate action to fully insert all Immediately Required Action D.1 insertable control rods in core and referenced in cells containing one or more fuel Table 3.3.1.1-1. assemblies.

I. As required by 1.1 Ini-iate alternate method to detect 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action D.1 and suppress thermal hydraulic and referenced in instability oscillations.

Table 3.3.1.1-1. AND 1.2 Restore required channels to 120 days OPERABLE.

J. Required Action and J.1 Reduce THERMAL POWER to 4 hoirs associated Completion <25% RTP.

Time of Condition I not met.

SUSQUEHANNA - UNIT 2 TS / 3.3-2 AmendmentIs1 207

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

---

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

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may toe delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. '12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.1.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.1.1.3 - ----- NOTE -------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 2 25% RTP.

Verify the absolute difference between the average 7 days power range monitor (APRM) channels and the calculated power is < 2% RTP plus any gain adjustment required by LCO 3.2.4. "Average Power Range Monitor (APRM) Setpoints" whie operating at 2 25% RTP.

SR 3.3.1.1.4 ------------------------------- NOTE----------------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

SUSQUEHANNA - UNIT 2 TS /3.3-3 Amendment VA,207

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.11 ---------------------------- NOTES-------------------

1. Neutron detectors are excluded.

2. For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL CALIBRATION. 184 days SR 3.3.1.1.12 ------------------------------ NOTES --------------------------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST 184 days SR 3.3.1.1.1 3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.1 5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.1 6 Verify Turbine Stop Valve-Closure and Turbine Control 24 months Valve Fast Closure, TriD Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 30% RTP.

(continued)

SUSQUEHANNA - UNIT 2 TS' /3.3-5 Amendment A~5,20()7

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.17 ---------- ------------- NOTES-- ------------------------

1. Neutron detectors are excluded.

2. For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

3. For Function 2.e, "n" equals 8 channels for the purpose of determining the STAGGERED TEST BASIS Frequency. Testing of APRM and OPRM outputs shall alternate.

Verify the RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS SR 3.3.1.1.18 ---------------------------- NOTES------------------------------

1. Neutron detectors are excluded.

2. For Functions 2 b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION 24 months SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM Simulated 24 months Thermal Power is i 30% and recirculation drive flow is

< value equivalent to the core flow value defined in the COLR.

SR 3.3.1.1.20 Adjust recirculation drive flow to conform to reactor core 24 months flow. l SUSQUEHANNA-UNIT 2 TS, / 3.3-6 Amendment *6s 207

PPL Rev. 2 3.3.1.1 Table 3.3.1.1-1 (page 1of 3)

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

1. Intermediate Range Monitors

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

• 1221125 divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

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

2. Average Power Range Monitors

a. Neutron 2 3(c) G SR 3.3.1.1.2 *20% RTP Flux-High SR 3.3.1.1.7 (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18

b. Simulated 1 3(C) F SR 3.3.1.1.2 *0.58W Thermal SR 3.3.1.1.3 +62%RTP and Power-High SR 3.3.1.1.8 *115.5%RTP SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.20 (continued)

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

(b) 0.58(W-AW) + 62% RTP when reset for single IooF operation per LCO 3.4.1, Recirculation Loops Oper2ting.'

For single-loop operation, the value of AW = 50 /60.58. For two-loop operation, the value of AW = 0. I (c) Each APRM channel provides Inputs to both trip systems.

SUSQUEHANNA - UNIT 2 TS / 3.3-7 Amendment tSo, i0, 207

PPL Rev. 2 RF'S Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

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

2. Average Power Range Monitors (continued)

c. Neutron 1 F SR 3.3.1.1.2 S 120% RTP Flux-High SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.12 l SR 3.3.1.1.18

d. Inop 1,2 G SR 3.3.1.1.12 NA

e. 2-Out-Of-4 1,2 2 G SR 3.3.1.1.2 NA Voter SR 3.3.1.1.12 SR 3.3.1.1.15 SR 3.3.1.1.17

f. OPRM Trip 225% RTP 3 (c) l SR 3.3.1.1.2 Id)

SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.19 SR 3.3.1.1.20

3. Reactor Vessel 1,2 2 G SR 3.3.1.1.9 S 1093 psig Steam Dome SR 3.3.1.1.10 Pressure-High SR 3.3.1.1.15

4. Reactor Vessel 1,2 2 G SR 3.3.1.1.1 2 11.5 inches Water Level- SR 3.3.1.1.9 Low, Level 3 SR 3.3.1.1.10 SR 3.3.1.1.15

5. Main Steam 1 8 F SR 3.3.1.1.9 s 11% closed Isolation SR 3.3.1.1.13 Valve-Closure SR 3.3.1.1.15 SR 3.3.1.1.17

6. Drywell 1,2 2 G SR 3.3.1.1.9 5 1.88 psig Pressure-High SR 3.3.1.1.10 SR 3.3.1.1.15 (continued)

(continued)I (c) Each APRM channel provides inputs to both trip systems.

(d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

SUSQUEHANNA - UNIT 2 TS, / 3.3-8 .Amendment16, 20 7

PPL Rev. 2 PPL Rev. ORPS Instrumentation 3.3.1 .1 Table 3.3.1.1-1 (page 3 of 3)

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

7. Scram Discharge Volume Water Level-High

a. Level 1,2 2 G SR 3.3.1.1.9 S 66 gallons Transmitter SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 2 H SR 3.3.1.1.9 S 66 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

b. Float Switch 1,2 2 G SR 3.3.1.1.9 S 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 2 H SR 3.3.1.1.9 s 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

8. Turbine Stop 2 30% RTP 4 E SR 3.3.1.1.9 S 7% closed Valve-Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

9. Turbine Control > 30% RTP 2 E SR 3.3.1.1.9 2 460 psig Valve Fast SR 3.3.1.1.13 Closure, Trip SR 3.3.1.1.15 Oil Pressure- SR 3.3.1.1.16 Low SR 3.3.1.1.17

10. Reactor Mode 1,2 2 G SR 3.3.1.1.14 NA I Switch- SR 3.3.1.1.15 Shutdown Position 5 (a) 2 H SR 3.3.1.1.14 NA I SR 3.3.1.1.15

11. Manual Scram 1,2 2 G SR 3.3.1.1.5 NA

. SR .3.3.1.1,15.

5(a) 2 H SR 3.3.1.1.5 NA SR 3.3.1.1.15 (a) With any control rod withdrawn from a core cell conmaining one or more fuel assemblies.

SUSQUEHANNA - UNIT 2 T-S)/ 3.3-9 Amendment 181, 207

PPL Rev. 1 Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

---

- I r------------------- - ------- - -------------- - ------------- -----

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 134 days I SR 3.3.2.1.2 - -- ------------- NOTE-----------------------------------

Not required to be perfornted until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at < 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 -------------------------------- NOTE-----------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.4 ------------------ ----------- NOTE------------------------------------

Neutron detectors are excluded.

Verify the RBM trip functions are not bypassed when 24 months THERMAL POWER is 2 3D% RTP.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL 24 months POWER is < 10% RTP.

SUSQUEHANNA - UNIT 2 T%'3/ 3.3-18 Amendment 16i, 207

PPL Rev. 1 Control Rod Blo-k Instrumentation 3.3.2.1 Table 3.3.2.1 -1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Rod Block Monitor

a. Low Power Range- 1(a) 2 SR 3.3.2.1.1 S0.58W+55%(b)

Upscale SR 3.3.2.1.A SR 3.3.2.1.7

b. Inop 1(a) 2 SR 3.3.2.1.1 NA SR 3.3.2.1.4

c. Downscale 1(a) 2 SR 3.3.2.1.1 2 3/125 divisions of SR 3.3.2.1.4 full scale SR 3.3.2.1.7

2. Rod Worth Minimizer 1(c), 2(c) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3. Reactor Mode Switch- (d) 2 SR 3.3.2.1.6 NA Shutdown Position (a) When THERMAL POWER is 2 30% RPT (b) 0.58(W-AW) + 55% RTP when reset for single-loop operation per LCO 3.4.1, 'Recirculation Loops Operating".

For single-loop operation, the value of AW = 5%/0.58. For two-loop operation, the value of AW = 0.

(c) With THERMAL POWER 5 10% RTP.

I (d) Reactor mode switch in the shutdown position.

SUSQUEHANNA - UNIT 2 TS /3.3-20 Arnendment IZI, 207

PPL Rev. 3 Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

OR One recirculation loop may be in operation 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 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%.

---

ole --

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: MC)DES 1 and 2.

SUSQUEHANNA - UNIT 2 TS.1 3.4-1 Amendment 1-51, 1tEB, A.9, t92, 20n7

PPL Rev. 1 SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation,' MODE 2 requirements for Functions 2.a, 2.d and 2.e of Table 3.3.1.1-1; I

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 oe Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence.

OR

2. Conformance to the approved rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals that are not in conformance with the BPWS shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CFD charging water header pressure Ž 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

SUSQUEHANNA - UNIT 2 TS / 3.10-20 Amendmentts, 207

PPL Rev. 1 SDM Test - Refueling 3.10.8 ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------- NOTE- -----------------------NOTE---------------

Separate Condition entry Rod worth minimizer may be is allowed for each control bypassed as allowed by LCO rod. 3.3.2.1, "Control Rod Block

- -Instrumentation," if required, One or more control rods to allow insertion of not coupled to its inoperable control rod and associated CRD. continued operation.

A.1 Fully insert inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> control rod.

AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.2 Disarm the associated CRD.

B. One or more of the above B.1 Place the reactor mode Immediately requirements not met for switch in the shutdown reasons other than or refuel position.

Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to the applicable LCO 3.3.1.1, Functions 2.a, 2.d and 2.e of SRs Table 3.3.1.1-1.

(continued)

SUSQUEHANNA - UNIT 2 TS /3.10-21 Amendment ItE1, 207

PPL Rev. 4 Reporting Requirements 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 submit:ed 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;

5. The Shutdown Margin for Specification 3.1.1; and

6. Oscillation Power Range Monitor (OPRM) Trip setpoints, for Specification 3.3.1.1.

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 N/Wt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meier (LEFM/Tm) as described in the LEFM, MTopical Report and supplement referenced below.

When feedwater flow measurements from the LEFM/TM system are not available, the (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 1.69, 190, 1-92, 207