ML18239A196

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Attachment - Vogtle Electric Generating Plant Unit 3
ML18239A196
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 09/27/2018
From: Paul Kallan
NRC/NRO/DLSE/LB4
To:
Southern Nuclear Operating Co
KALLAN P/415-2809
Shared Package
ML18239A192 List:
References
EPID L-2017-LLA-0097, LAR-17-031
Download: ML18239A196 (17)
v • d • e


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 144 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-91 REMOVE INSERT 7 7 Appendix A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.1.3-1 3.1.3-1 3.1.3-2 3.1.3-2 3.2.1-1 3.2.1-1 3.2.1-2 3.2.1-2 3.2.1-4 3.2.1-4 3.2.1-5 3.2.1-5 3.2.2-1 3.2.2-1 3.2.2-2 3.2.2-2 3.2.2-3 3.2.2-3 3.2.5-1 3.2.5-1 3.3.1-2 3.3.1-2 3.3.1-3 3.3.1-3 3.7.1-2 3.7.1-2 5.6-4 5.6-4 5.6-5 5.6-5

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 144, are hereby incorporated into this license.

(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 144

Technical Specifications MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR.

APPLICABILITY: MODE 1 for the upper MTC limit.

MODE 2 with keff 1.0 for the upper MTC limit.

MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Restore MTC within limit. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion keff < 1.0.

Time of Condition A not met.

C. MTC not within lower C.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC within upper limit. Once prior to entering MODE 1 after each refueling VEGP Units 3 and 4 3.1.3 - 1 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications MTC 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.3.2 -----------------------------------------------------------------------

- NOTES -

1. Not required to be performed provided applicable criteria in the COLR are satisfied.
2. Not required to be performed if the MTC measured at the equivalent of equilibrium RTP all rods out (ARO) boron concentration of 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.

Verify MTC is within lower limit. Once within 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP ARO boron concentration of 300 ppm AND 14 EFPD thereafter when MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR VEGP Units 3 and 4 3.1.3 - 2 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) (Constant Axial Offset Control (CAOC) W(Z)

Methodology)

LCO 3.2.1 FQ(Z), as approximated by FQC ( Z) and FQW ( Z) , shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP and with On-Line Power Distribution Monitoring System (OPDMS) not monitoring parameters.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1 Reduce THERMAL 15 minutes after each

- NOTE - POWER 1% RTP for FQC ( Z) determination Required Action A.3 each 1% FQC ( Z) exceeds shall be completed limit.

whenever this Condition is entered. AND A.2 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each FQC ( Z) not within limit. setpoints 1% for each FQC ( Z) determination 1% FQC ( Z) exceeds limit.

AND A.3 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 VEGP Units 3 and 4 3.2.1 - 1 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. -------------------------------- B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

- NOTE - POWER 1% for each Required Action B.3 1% FQW ( Z ) exceeds limit.

shall be completed whenever this Condition AND is entered.

B.2 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> setpoints 1% for each FQW ( Z) not within limits. 1% FQW ( Z ) exceeds limit.

AND B.3 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action B.1 C. Required Action and C.1 Reduce THERMAL 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion POWER < 25% RTP.

Time not met.

VEGP Units 3 and 4 3.2.1 - 2 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3 -----------------------------------------------------------------------

- 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 OPDMS not monitoring parameters.

Verify FQC ( Z ) within limit. Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQC ( Z ) was last verified AND 31 effective full power days (EFPD) thereafter VEGP Units 3 and 4 3.2.1 - 4 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.4 -----------------------------------------------------------------------

- NOTES -

1. 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 OPDMS not monitoring parameters.
2. If FQW ( Z) measurements indicate maximum over z FQC ( Z ) has increased since the previous evaluation of FQC ( Z ) :
a. Increase FQW ( Z ) by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify FQW ( Z ) is within limits; or
b. Repeat SR 3.2.1.4 once per 7 EFPD until two successive flux maps indicate maximum over z FQC ( Z ) has not increased.

Verify FQW ( Z) within limits. Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilib-rium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQW ( Z) was last verified AND 31 EFPD thereafter VEGP Units 3 and 4 3.2.1 - 5 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FNH )

LCO 3.2.2 FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP and with On-Line Power Distribution Monitoring System (OPDMS) not monitoring parameters.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1.1 Restore FNH to within limit. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

- NOTE -

Required Actions A.2 OR and A.3 must be completed whenever A.1.2.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Condition A is entered. POWER to < 50% RTP.

AND FNH not within limits.

A.1.2.2 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> setpoints to 55% RTP.

AND A.2 Perform SR 3.2.2.1. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND VEGP Units 3 and 4 3.2.2 - 1 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FNH 3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 ------------------------------------

- NOTE -

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER reaching 95% RTP B. Required Action B.1 Reduce THERMAL 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated POWER to < 25% RTP.

Completion Time not met.

VEGP Units 3 and 4 3.2.2 - 2 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications FNH 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 -----------------------------------------------------------------------

- NOTE -

Not required to be performed if OPDMS was monitoring parameters upon exceeding 75% RTP.

Verify FNH within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 75% RTP SR 3.2.2.2 -----------------------------------------------------------------------

- 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 OPDMS not monitoring parameters.

Verify FNH within limits specified in the COLR. 31 effective full power days (EFPD)

VEGP Units 3 and 4 3.2.2 - 3 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications OPDMS-Monitored Parameters 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 On-Line Power Distribution Monitoring System (OPDMS)-Monitored Parameters LCO 3.2.5 The following parameters shall not exceed their operating limits as specified in the COLR:

a. Peak Linear Heat Rate;
b. FNH ;
c. DNBR; and
d. SDM.

APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP and with OPDMS monitoring parameters a, b, and c.

MODE 1 with OPDMS monitoring parameter d.

MODE 2 with keff 1.0 and OPDMS monitoring parameter d.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Restore all parameters to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> parameters a. through within limits.

c. above not within limits.

B. Required Action B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and associated POWER to < 25% RTP.

Completion Time of Condition A not met.

C. Parameter d above not C.1 Initiate boration to restore 15 minutes within limits. SDM to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 Verify the parameters a. through d. to be within their 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limits.

VEGP Units 3 and 4 3.2.5 - 1 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Reduce THERMAL 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and POWER to < P-10.

referenced in Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS

- NOTE -

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.2 -----------------------------------------------------------------------

- NOTES -

1. Required to be met within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching 15% RTP.
2. If the calorimetric heat balance is 15% RTP, and if the nuclear instrumentation channel indicated power is:
a. lower than the calorimetric measurement by

> 5% RTP, then adjust the nuclear instrumentation channel upward to match the calorimetric measurement.

b. higher than the calorimetric measurement, then no adjustment is required.

Compare results of calorimetric heat balance to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> nuclear instrument channel output.

VEGP Units 3 and 4 3.3.1 - 2 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3 -----------------------------------------------------------------------

- NOTES -

1. Adjust the conversion factor, T°, in the T power calculation (qT) if absolute difference between qT and the calorimetric measurement is > 3% RTP.
2. Required to be met within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching 50% RTP.
3. If the calorimetric heat balance is < 70% RTP, and if qT is:
a. lower than the calorimetric measurement by

> 5%, then adjust T° to match the calorimetric measurement.

b. higher than the calorimetric measurement, then no adjustment is required.

Compare results of calorimetric heat balance to the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> T power calculation (qT) output.

SR 3.3.1.4 -----------------------------------------------------------------------

- NOTES -

1. Adjust nuclear instrument channel in PMS if absolute difference is 1.5% AFD.
2. Required to be met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 20% RTP.

Compare results of the incore detector measurements 31 effective full to nuclear instrument channel AXIAL FLUX power days DIFFERENCE. (EFPD)

SR 3.3.1.5 -----------------------------------------------------------------------

- NOTE -

Required to be met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 50% RTP.

Calibrate excore channels to agree with incore 92 EFPD detector measurements.

VEGP Units 3 and 4 3.3.1 - 3 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------------------------------------

- NOTE -

Only required in MODE 1.

Reduce the Overpower T 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> reactor trip setpoints to less than or equal to the Maximum Allowable %

RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

B. One or both steam B.1 Restore MSSV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> generators with one or OERABLE status.

more MSSVs inoperable for closing.

C. Required Action C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion Time of AND Condition A not met.

C.2 Be in MODE 4 with the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR RCS cooling provided by the RNS.

One or both steam generators with 5 MSSVs inoperable for opening.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not AND met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> VEGP Units 3 and 4 3.7.1 - 2 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

6. APP-GW-GLR-137, Revision 1, Bases of Digital Overpower and Overtemperature Delta-T (OPT/OTT) Reactor Trips, Westinghouse Electric Company LLC.

(Methodology for Specification 2.1.1 - Reactor Core Safety Limits.)

7a. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004 (Westinghouse Proprietary) and WCAP-16045-NP-A, (Non-Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

7b. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007 (Westinghouse Proprietary) and WCAP-16045-NP-A, Addendum 1-A, (Non-Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

7c. WCAP13749PA, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 (Westinghouse Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems 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.

5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

3.4.3, RCS Pressure and Temperature (P/T) Limits; and 3.4.14, Low Temperature Overpressure Protection (LTOP).

VEGP Units 3 and 4 5.6 - 4 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

Technical Specifications Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

WCAP-14040-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves.

(Limits for LCO 3.4.3 and LCO 3.4.14).

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto.

5.6.5 Post Accident Monitoring Report When a report is required by Condition B of LCO 3.3.17, 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.

5.6.6 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.4, "Steam Generator (SG) Program." The report shall include:

a. The scope of inspections performed on each SG,
b. Active degradation mechanisms found,
c. Nondestructive examination techniques utilized for each degradation mechanism,
d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
f. Total number and percentage of tubes plugged to date,
g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and
h. The effective plugging percentage for all plugging in each SG.

VEGP Units 3 and 4 5.6 - 5 Amendment No. 144 (Unit 3)

Amendment No. 143 (Unit 4)

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