PLA-6603, Extended Power Uprate Master Test Procedure TP-199-013
| ML100910477 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/26/2010 |
| From: | Rausch T Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6603 TP-199-013 | |
| Download: ML100910477 (72) | |
Text
Timothy S. Rausch Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com
- sale#
U.-b P P TM MAR 2 6 o010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 EXTENDED POWER UPRATE MASTER TEST PROCEDURE TP-199-013 RENEWED OPERATING LICENSE NO. NPF-14 PLA-6603 Docket No. 50-387 Attached is the Susquehanna Steam Electric Station (SSES) Unit 1 Extended Power Uprate (EPU) Phase 2 Master Test Procedure (TP-199-013, Revision 0). This procedure will guide the overall Unit 1 Phase 2 EPU test program from start up to the EPU licensed power level of 3952 MWt.
This additional information is provided at the request of the NRC Project Manager for Susquehanna.
If you have any questions or require additional information, please contact Mr. Duane L. Filchner at (610) 774-7819.
Attachment:
TP-199-013, Unit 1 Phase 2 EPU Master Test Procedure (Special, Infrequent or Complex Test/Evolution)
Copy:
NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/BRP Mr. B. K. Vaidya, NRC Project Manager
Attachment to PLA-6603 TP-199-013, Unit 1 Phase 2 EPU Master Test Procedure (Special, Infrequent Or Complex Test/Evolution)
For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE UNIT 1 PHASE 2 EPU MASTER TEST PROCEDURE (SPECIAL, TP-199-013 INFREQUENT OR COMPLEX TEST/EVOLUTION)
Revision 0 Page 1 of 70 ADHERENCE LEVEL: STEP-BY-STEP QUALITY CLASSIFICATION:
APPROVAL CLASSIFICATION:
(X)
QA Program
( ) Non-QA Program (X)
Plant
( ) Non-Plant
( )
Instruction EFFECTIVE DATE:
PERIODIC REVIEW FREQUENCY:
N/A PERIODIC REVIEW DUE DATE:
N/A RECOMMENDED REVIEWS:
Operations, Reactor Engineering, EPU Engineering, Station Engineering, PORC Procedure Owner:
Fred Graber Responsible Supervisor:
SE Supervisor-Mechanical Responsible FUM:
Manager-Station Engineering Responsible Approver:
Plant Manager FORM NDAP-QA-0002-1, Rev. 4, Page 1 of 1 (Electronic Form)
For Information Only TP-199-013 Revision 0 Page 2 of 70 PROCEDURE REVISION
SUMMARY
TITLE:
UNIT 1 PHASE 2 EPU MASTER TEST PROCEDURE (SPECIAL, INFREQUENT OR COMPLEX TEST/EVOLUTION) 1 )
New issue - developed using TP-299-01 0 as a guide.
For Information Only TP-199-013 Revision 0 Page 3 of 70 TABLE OF CONTENTS SECTION PAGE
- 1.
PURPOSE/SCOPE 6
- 2.
DISCUSSION 6
- 3.
REFERENCES 8
- 4.
TEST EQUIPMENT 11
- 5.
PRECAUTIONS/NOTES 11
- 6.
PREREQUISITES 12
- 7.
PROCEDURE 14 7.1 Mode 5 / Mode 4 Testing 14 7.2 Preparations for entering Mode 2 14 7.3 Startup to 83% Power and Test Condition A Testing 16 7.4 Test Condition B Testing 20 7.5 Test Condition C Testing 21 7.6 Preparation for Power Ascension Above 3733 MWt (94.4%)
23 7.7 (Start of SICTIE Section) Initial power ascension above 3733 MWt.
25 7.8 Test Condition D Testing 29 7.9 Preparation for Power Ascension Above 3855 MWt (97.5%)
31 7.10 (Start of SICT/E Section) Initial power ascension above 3855 MWt (97.5%).
33 7.11 Test Condition E Testing 38 7.12 TC E Testing at 100 MIb/Hr Core Flow 39 7.13 TC E Testing at 108 MIb/Hr Core Flow 40 7.14 Test Condition E Review 40
For Information Only TP-199-013 Revision 0 Page 4 of 70 TABLE OF CONTENTS (Cont'd)
SECTION
- 8.
RESTORATION
- 9.
ACCEPTANCE CRITERIA
- 10.
REVIEW
- 11.
RECORDS PAGE 41 42 42 42 ATTACHMENTS ATTACHMENT A
B C
D E
F G
H J
K L
M N
0 Test Control Documentation EPU Test 42 - Required I&C Surveillances Test Condition A Review Summary EPU Test Condition Definitions Test Condition B Review Summary Test Condition C Review Summary ST-1 B Moisture Carryover Testing Unit 1 Station Verification of Activities for Power Ascension Test Condition D Review Summary EPU Test Program Power Ramp Data Test Condition E Review Summary ST-12B RBM Testing ST-12A APRM Testing ST-1 9 Core Performance Testing Test Plateau Review Record PAGE 43 44 45 47 48 49 50 51 52 53 54 56 57 58 59
For Information Only TP-1 99-013 Revision 0 Page 5 of 70 ATTACHMENTS ATTACHMENT P
Q R
S T
U V
W Deleted Final Test Program Review Record TP-199-013 Subtest Numbers ST-1A Chemical and Radiochemical ST-10 IRM Performance ST-2 Radiation Measurements ST-22 Pressure Regulator ST-24 Turbine Valve Surveillance PAGE 60 61 62 64 65 66 67 70
For Information Only TP-1 99-013 Revision 0 Page 6 of 70
- 1.
PURPOSE/SCOPE The purpose of this procedure is to provide a centralized mechanism for documenting completion of all items necessary to perform a successful Unit 1 Phase 2 Extended Power Uprate Test Program. Specifically, this procedure provides a method of:
1.1 Ensuring that requirements for commencing testing in each Test Condition are met (Refer to Section 2 for a definition of Test Condition) 1.2 Specifying testing to be completed during each Test Condition 1.3ý Tracking status of test implementation 1.4 Controlling escalation of Test Conditions
- 2.
DISCUSSION 2.1 This procedure does not supersede or replace any existing plant procedure, process or program.
2.2 This procedure performs no active testing. It is used as a master checklist and guide for the overall Unit 1 Phase 2 Extended Power Uprate Test Program.
2.3 In compliance and in conjunction with NDAP-QA-0406, this procedure imposes Administrative Controls throughout the EPU Test Program to direct reactor startup, power escalation and the establishment of Test Conditions.
2.4 A Test Condition (TC) is a defined range of reactor power and core flow conditions at which testing is conducted. The Test Condition also includes the startup path to those ranges. The Test Conditions for the Unit 1 Phase 2 EPU Test Program are as follows:
2.4.1 TC A - Reactor power less than 3733 MWt (94.4%) with any core flow within the safe operating region of the Power/Flow Map.
(Percent reactor power is specified in percent of 3952 MWt throughout this procedure.) This definition is from M-1563. Per Station Startup schedule, TC A is from Mode 5 through 3302 MWt (83.3%o +/-+.25%)
2.4.2 TC B - Reactor power between 3293 and 3360 MWt (83.3% and 85.0%) with any core flow within the safe operating region of the Power/Flow Map.
2.4.3 TC C - Reactor power between 3658 and 3733 MWt (92.6% and 94.4%) with any core flow within the safe operating region of the Power/Flow Map.
For Information Only TP-1 99-013 Revision 0 Page 7 of 70 2.4.4 TC D - Reactor power between 3779 and 3855 MWt (95.6% and 97.5%) with any core flow within the safe operating region of the Power/Flow Map.
2.4.5 TC E - Reactor power between 3873 and 3952 MWt (98.0% and 100%) with any core flow within the safe operating region of the Power/Flow Map.
2.5 A Test Plateau is an administrative grouping of one or more Test Conditions and/or plant conditions to support efficient control of test scheduling, results review and power escalation. The Test Plateaus for the Unit 1 Phase 2 EPU Test Program are as follows:
2.5.1 94.4% Power Test Plateau - Includes startup and operation up to and including 94.4% power which includes TC A, TC B, and TC C.
2.5.2 97.5% Power Test Plateau - Includes startup and operation up to and including 97.5% power which includes TC D.
2.5.3 100% Power Test Plateau - Includes startup and operation up to and including 100% power which includes TC E.
2.6 Attachments C, E, F, I and K specify the minimum tests that are required to be implemented in TC A, TC B, TC C, TC D and TC E, respectively. The EPU Subtest number specified in these attachments has the format of xy.z where:
2.6.1 xy is the "Test Number" specified in the test specification. x is a one to three digit number and is always present. y is an alphabetical character and is optional.
2.6.2 z is an arbitrary number used to distinguish specific partial implementations of the test xy when the test as specified in the test specification is not fully implemented in a Test Condition, or when more than one implementing procedure is required.
2.7 M-1 563 test specifications for Test 33 Piping Steady State Vibration and Test 100, Main Steam and Feedwater Piping Vibration overlap with each other, To clarify pipe vibration testing, Test 100 contains all testing required in M-1 563 for both Tests 33 and 100.
2.8 This procedure is not intended to control the sequence of EPU testing activities within a Test Condition unless otherwise noted. It does, however, provide a method for ensuring that all testing within each Test Condition is completed and ensures that all required reviews and prerequisites are satisfied during the transition from one Test Condition to the next.
For Information Only TP-199-013 Revision 0 Page 8 of 70 2.9 Those sections of this procedure that provide direction to initially increase power beyond 3733 MWt are classified as SICT/Es as these sections represent an expansion of station operation beyond current bounds of existing procedures or training and intensified test and evolution controls are required. Those sections contain SICT/E in their heading
- 3.
REFERENCES 3.1 CH-SY-026, Moisture Carryover 3.2 GO-1 00-002, Plant Startup, Heatup, and Power Operation 3.3 GO-100-004, Plant Shutdown to Minimum Power 3.4 HP-TP-521, Radiological Survey Program in Support of Extended Power Uprate Modification 3.5 NDAP-QA-0008, Procedure Writers Guide 3.6 NDAP-QA-0320, Special, Infrequent or Complex Test/Evolutions 3.7 NDAP-QA-0406, Extended Power Uprate Test Program 3.8 NDAP-QA-0450, Extended Power Uprate Project Implementation 3.9 NSEP-QA-0004, Station Engineering Surveillance and Technical Procedures Preparation and Performance Guidelines 3.10 OI-TA-008, Shift Technical Advisor Responsibilities 3.11 RE-081-036, Core Fuel Pool Verification 3.12 RE-OTP-201, TIP Uncertainty 3.13 RE-iTP-026, Validation of Core Thermal Power Heat Balance 3.14 SC-33-101, Ul TB Vent Weekly Iodine & Particulate Activity 3.15 SC-33-102, UI TB Vent Monthly Tritium & Grab Sample Analysis 3.16 SC-143-101, UI Main Condenser Air Ejector Monthly Noble Gas 3.17 SC-76-101, Ul Rx Coolant Conductivity Determination 3.18 SC-76-102, Ul Primary Coolant Specific Activity Dose Equivalent 1-131 3.19 SC-176-106, U1 Rx Coolant Chloride and pH Determination
For Information Only TP-1 99-013 Revision 0 Page 9 of 70 3.20 SE-164-305, Recirc MG Set Positioners High Speed Stops 3.21 SE-178-001, APRM 11 Drive Flow Calibration 3.22 SE-1 78-002, APRM 12 Drive Flow Calibration 3.23 SE-1 78-003, APRM 13 Drive Flow Calibration 3.24 SE-178-004, APRM 14 Drive Flow Calibration 3.25 SI-178-301A, Semi Annual Calibration IRM Channel A 3.26 SI-1 78-301 B, Semi Annual Calibration IRM Channel B 3.27 SI-178-301C, Semi Annual Calibration IRM Channel C 3.28 SI-178-301D, Semi Annual Calibration IRM Channel D 3.29 SI-178-301E, Semi Annual Calibration IRM Channel E 3.30 SI-1 78-301 F, Semi Annual Calibration IRM Channel F 3.31 SI-1 78-301G, Semi Annual Calibration IRM Channel G 3.32 Si-1 78-301 H, Semi Annual Calibration IRM Channel H 3.33 Sl-179-360, Setpoint Calibration Check of Main Steam Line (MSL) Radiation Monitor Channels RIS-D12-1K603A, B, C, D 3.34 SI-183-304, 24 Month Calibration of Main Steam Line A Flow Channels FIS-B21-1N006A&B and Main Steam Line B Flow Channels FIS-B21-1N007A&B 3.35 SI-1 83-305, 24 Month Calibration of Main Steam Line A Flow Channels FIS-B21-1N006C&D and Main Steam Line B Flow Channels FIS-B21-1N007C&D 3.36 SI-183-306, 24 Month Calibration of Main Steam Line C Flow Channels FIS-B21-1N008C&D and Main Steam Line D Flow Channels FIS-B21-1N009C&D 3.37. SI-183-307, 24 Month Calibration of Main Steam Line C Flow Channels FIS-B21-1N008A&B and Main Steam Line D Flow Channels FIS-B21-1N009A&B 3.38 SO-100-007, Daily Surveillance Operating Log 3.39 SO-178-004, Weekly APRM Calibration 3.40 SR-100-008, In Sequence Critical and Shutdown Margin Demo
For Information Only TP-199-013 Revision 0 Page 10 of 70 3.41 SR-155-004, Scram Time Measurements of Control Rods 3.42 SR-178-012, LPRM Calibration Validation 3.43 TP-055-001, CRD Stroke Time and Friction Measurement 3.44 TP-100-013, EPU Data Collection and Extrapolation 3.45 TP-144-048, Condensate Pump Trip 3.46 TP-145-029, Feedwater Master Water Level Controller MWLC Tuneup (SICT/E) 3.47 TP-162-030, Steam Dryer and Flow Induced Vibration Testing 3.48 TP-164-031, Core Flow Calibration 3.49 TP-193-041, EPU EHC Pressure Regulator Testing 3.50 TP-199-010, EPU Temperature Data Collection for Service Water 3.51 EC-PUPC-2069, Extended Power Uprate Flow Induced Vibration Testing and Walkdown Criteria 3.52 EC-PUPC-2097, Revised Susquehanna Replacement Steam Dryer Limit Curves
- Main Steam Line Mounted Instrumentation 3.53 M-1 563, Nuclear Engineering Specification for Extended Power Uprate Startup Testing 3.54 NRC 2009-0052, SSES UNITS I AND 2 RE: CONDENSATE PUMP TRIP TEST LICENSE CONDITION FOR SSES UNIT NOS I AND 2 (TAC NOS ME0223 AND ME0224) 3.55 PLA-6076, Proposed License Amendment Numbers 285 for Unit 1 Operating License No. NPF-14 and 253 for Unit 2 Operating License No. NPF-22, Constant Pressure Power Uprate 3.56 PLA-6242, Susquehanna Steam Electric Station Proposed License Amendment No. 285 for Unit 1 Operating License No. NPF-14 and Proposed License Amendment No. 253 for Unit 2 Operating License No. NPF-22 Extended Power Uprate Application Regarding Steam Dryer and Flow Effects Request For Additional Information Responses 3.57 SSES Unit 1 Operating License NPF-14 Amendment 246
For Information Only TP-1 99-013 Revision 0 Page 11 of 70
- 4.
TEST EQUIPMENT No specific M&TE equipment is necessary to perform this procedure.
- 5.
PRECAUTIONS/NOTES 5.1 Sections and steps within sections must be completed in the order listed unless otherwise specified.
5.2 Tests identified in the Test Condition Review Summary Attachments may be completed in any order unless otherwise specified.
5.3 Per Unit 1 Operating License Condition 2.C. (36) (d), the following key attributes of the PATP (Power Ascension Test Program) shall not be made less restrictive without prior NRC approval.
5.3.1 During initial power ascension testing above 3733 MWt, each test plateau increment shall be approximately 3.5% of 3489 MWt (122 MWt);
5.3.2 Level 1 performance criteria; and 5.3.3 The methodology for establishing the stress criteria used for the Level 1 and Level 2 performance criteria Changes to other aspects of the PATP may be made in accordance with the guidance of Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitments," issued July 1999.
5.4 Per Unit I Operating License Condition 2.C.(36) (a) 3, PPL shall hold the facility at each 3.5% ascension step above 3489 MWt to collect data, conduct plant inspections and walk-downs, and evaluate steam dryer performance based on the data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt of transmission.
5.5 Per Unit 1 Operating License Condition 2.C (36) (a) 4, If any frequency peaks from the MSL strain gauge data exceeds the limit curve for the MSL strains above 107% of 3489 MWt, PPL shall return the facility to a power level at which the acceptance criteria is not exceeded. PPL shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.
For Information Only TP-1 99-013 Revision 0 Page 12 of 70 5.6 Per Unit 1 Operating License Condition 2.C (36) (a) 5, In addition to evaluating the dryer instrumentation data and MSL strain gauge data, PPL shall monitor reactor pressure vessel water level instrumentation and MSL piping accelerometers during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, PPL shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.
5.7 Per Unit I Operating License Condition 2.C (37) (b), Unless the NRC issues a letter notifying the licensee that the tests specified by Licensee Condition 2.C.(37)(a) adequately demonstrate that a single condensate pump trip will not result in a loss of all feedwater while operating at the full CPPU power level of 3952 MWt, PPL shall perform the transient test on either SSES unit (whichever unit is first to achieve the following specified operating conditions) specified by License Condition 2.C.(37)(a) during the power ascension test program while operating at 3872 MWt to 3952 (98% to 100% of the full CPPU power level) with feedwater and condensate flow rates stabilized.
NRC letter 2009-0052 was received which provided relief for performing the Condensate Pump trip test while operating at 3872 MWt to 3952 MWt (98% -
100% of full CPPU power level) as long as the test is performed following all modifications on the Feedwater and Condensate Systems at conditions specified under Unit I Operating License Condition 2.C (37) (a) demonstrating that a trip of a single Condensate Pump would not result in a total loss of Feedwater when operating at 3872 MWt to 3952 MWt.
- 6.
PREREQUISITES 6.1 A SICT/E Analysis, Form NDAP-QA-0320-1, has been completed by the Test Director/Evolution Coordinator and attached to this procedure prior to procedure implementation.
Confirmed By Date 6.2 PPL has provided the NRC with the benchmark results and updated MSL limit curves to support power ascension above 3733 MWt as required by License Condition 2.C.(36)(b)2.
Date Provided Confirmed By Date
For Information Only TP-199-013 Revision 0 Page 13 of 70 6.3 Administrative Hold Condition for restricting entry into Mode 2 has been initiated as follows:
o 6.3.1 ZWO document specifying Administrative Hold Condition has been issued.
ZWO number:
O 6.3.2 Unit 1 Shift Supervision has been informed of Administrative Hold Condition and to include the hold condition in the Unit Supervisor Turnover Sheet.
Q 6.3.3 Work Week Management has been informed to add the Administrative Hold Condition and associated ZWO number as a Log Line to the appropriate activity in the station schedule.
Confirmed By Date 6.4 Administrative Hold Condition for reactor power not to exceed 3733 MWt (94.4%)
has been initiated as follows:
o 6.4.1 ZWO document specifying Administrative Hold Condition has been issued.
ZWO number:
O3 6.4.2 Unit I Shift Supervision has been informed of Administrative Hold Condition and to include the hold condition in the Unit Supervisor Turnover Sheet.
0 6.4.3 Work Week Management has been informed to add the Administrative Hold Condition and associated ZWO number as a Log Line to the appropriate activity in the station schedule.
Confirmed By Date 6.5 Administrative Hold Condition for reactor power not to exceed 3855 MWt (97.5%)
has been initiated as follows:
o3 6.5.1 ZWO document specifying Administrative Hold Condition has been issued.
ZWO number:
For Information Only TP-199-013 Revision 0 Page 14 of 70 O3 6.5.2 Unit I Shift Supervision has been informed of Administrative Hold Condition and to include the hold condition in the Unit Supervisor Turnover Sheet.
o 6.5.3 Work Week Management has been informed to add the Administrative Hold Condition and associated ZWO number as a Log Line to the appropriate activity in the station schedule.
Confirmed By7 Date
- 7.
PROCEDURE NOTE (1):
Sections and steps within sections must be completed in the order listed unless otherwise specified.
NOTE (2):
Tests identified in an Attachment may be completed in any order unless otherwise specified.
7.1 Mode 5 / Mode 4 Testing O3 7.1.1 Confirm that Shift Supervision is aware that testing identified in Attachment C, Test Condition A Review Summary for Mode 5 or Mode 4 may commence.
Confirmed By Date (Shift Supervision) o7.1.2 Perform tests listed in Attachment C, Test Condition A Review Summary that are specified for Mode 5 and Mode 4.
7.2 Preparations for entering Mode 2
[NOTE:
Steps 7.2.1 through 7.2.3 may be completed in any order._
7.2.1 Confirm the following:
oa.
All testing listed in Attachment C. Test Condition A Review Summary with additional plant condition requirements of Mode 4 or Mode 5 with the exception of ST 5.2 has been successfully completed OR Test Exception Reports have been written. ST 5.2 may be completed anytime prior to exceeding 1580 MWt (40%) when reactor pressure is greater than or equal to 800 psig.
For Information Only TP-1 99-013 Revision 0 Page 15 of 70 o
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment C have been reviewed by the TP-199-013 Test Director or EPU Test Program Director OR Test Exception Reports have been written.
o
- c.
All Test Exception Reports have been dispositioned.
O
- d.
There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Mode 2.
Confirmed By Date (EPU Test Prog Director)
O 7.2.2 Confirm that partial closure 4 of EC 690275, Extended Power Uprate Implementation has been completed.
Confirmed By Date Q3 7.2.3 Confirm that all items in GO-100-002, Attachment A, Unit 1 Station Verification of Activities for Entering Mode 2 have been signed off.
Confirmed By Date (Shift Supervision) 7.2.4 Obtain permission to perform following:
Ol
- a.
Enter Mode 2.
o
- b.
Increase reactor thermal power with plant conditions not to exceed 3733 MWt (94.4%) or 108 Mlbm/Hr core flow.
o
- c.
Perform all remaining tests listed in Attachment C, Test Condition A Review Summary.
O3
- d.
Perform all tests listed in Attachments E, Test Condition B Review Summary.
O
- e.
Perform all tests listed in Attachments F, Test Condition C Review Summary.
Plant Manager Date
For Information Only TP-199-013 Revision 0 Page 16 of 70 Q
7.2.5 Inform Unit 1 Shift Supervision that the Administrative Hold Condition for entering Mode 2 (prerequisite 6.3) has been lifted AND to Perform following:
- a.
Close ZWO issued in prerequisite 6.3.
o
- b.
Remove the Administrative Hold Condition from Unit Supervisor Turnover Sheet.
Confirmed By Date (Shift Supervision) 7.3 Startup to 83% Power and Test Condition A Testing o
7.3.1 Enter Mode 2.
time date o3 7.3.2 Ensure Shift Supervision is cognizant of the Administrative Hold Condition that Reactor power may not exceed 3733 MWt (94.4%)
initiated in prerequisite 6.3 until this Administrative Hold Condition is lifted by this TP or as otherwise notified by the Plant Manager.
Reactor thermal power may briefly exceed 3733 MWt during minor power transients inherent to approved test procedures.
Confirmed By Date o
7.3.3 Confirm that Shift Supervision is aware that all tests listed in Attachment C, Test Condition A Review Summary can be performed in any order at reactor power levels not to exceed 3302 MWt (83.3% +/-.25%) or at lower power levels as specified in Attachment C. Reactor thermal power may briefly exceed 3302 MWt during minor power transients inherent to approved test procedures.
Confirmed By Date (Shift Supervision)
Q 7.3.4 DURING approach to Initial Criticality, Perform ST-4, In Sequence Critical and Shutdown Margin Demonstration.
For Information Only TP-1 99-013 Revision 0 Page 17 of 70 Q
7.3.5 Commence collection of Pressure Regulator Incremental Regulation data per ST-22.1. This data should be collected (from Generator sync) at intervals not to exceed 3% (of scale) reactor power.
NOTE:
IF Reactor Power is ever reduced below 16%, AND the Reactor Mode is changed from Mode I to Mode 2, THEN ST-10.2 IRM/APRM overlap is required to be performed. This overlap check is only valid if an APRM calibration was performed while in Mode 1 prior to entering Mode 2.
0 7.3.6 Perform ST-22.2 Scram Bypass Setpoint Verification during power ascension. This should occur prior to exceeding 26% power (1027 MWt).
0 7.3.7 Continue power ascension AND Complete ST 5.2, Control Rod Scram Time Measurement for any required remaining control rods not previously tested prior to exceeding 40% power (1580 MWt).
O3 7.3.8 Continue power ascension to 60% power.
7.3.9 Perform Pressure Regulator testing.
o1
- a.
Complete TP-199-013 Attachment V, ST-22 Pressure Regulator to satisfy requirements for ST-22.1 performance up to and including 60% power.
o1
- b.
Confirm that Reactor Engineering has performed an assessment of margin to APRM Rod Block and Scram setpoints as well as margin to fuel thermal and preconditioning limits AND Deems margins to be acceptable for performance of ST-22.2, Pressure Regulator Step Changes and Pressure Regulator Failure.
Confirmed By Date (Reactor Engineering) o
- c.
Perform ST-22.2, Pressure Regulator Step Changes and Pressure Regulator Failure.
13 7.3.10 Continue power ascension to 65% power.
For Information Only TP-199-013 Revision 0 Page 18 of 70 7.3.11 At approximately 65% power, Perform following vibration testing in accordance with TP-162-030.
O3
- a.
Maintain reactor power within a tolerance of +/- 12 MWt as displayed on PICSY point NBA01.
O3
- b.
Record two 3 minute segment datasets of MSL Strain Gauges.
o1
- c.
AFTER the MSL Strain Gauge datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
o
- d.
Record reactor operating conditions at the time MSL data.
is recorded by completing Pt data sheet.
o
- e.
Inform Operations that the tolerance of +/- 12 MWt on reactor power is no longer in effect.
O
- f.
Evaluate dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.
Confirmed By Date (EPU Engineering)
O 7.3.12 Inform Operations that vibration test results are acceptable and that reactor power level may be increased per station schedule to 83.3% (3293 MWt) :.25% (3283 - 3302 MWt).
O 7.3.13 Perform remaining tests listed in Attachment C.
7.3.14 Perform following 83.3% vibration testing in accordance with TP-162-030:
o3
- a.
Maintain reactor power between 3283 MWt and 3302 MWt (83.3% t.25%) as displayed on PICSY point NBA01.
o3
- b.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
- c.
Perform walkdown of accessible areas.
- d.
Perform walkdown of inaccessible areas.
For Information Only TP-199-013 Revision 0 Page 19 of 70
- e.
Perform MSL Strain Gauge dataset recordings:
o (1) Record two 3-minute segment datasets of MSL Strain Gauges.
O (2)
AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
0 (3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
o
- f.
Record a dataset of MSL, FW, and Extraction Steam accelerometers.
o
- g.
Record a dataset of Recirculation and RHR Strain Gauges.
O
- h.
Inform Operations that the minimum power level of 3283 MWt is no longer in effect.
- 0
- i.
Evaluate dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.
Confirmed By Date (EPU Engineering) 7.3.15 Confirm the following:
o
- a.
All testing listed in Attachment C, Test Condition A Review Summary has been successfully completed OR Test Exception Reports have been written.
o
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment C have been reviewed by the.
TP-199-013 Test Director or EPU Test Program Director OR Test Exception Reports have been written.
- c.
All Test Exception Reports have been dispositioned.
For Information Only TP-199-013 Revision 0 Page 20 of 70
- d.
There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition B.
Confirmed By Date (EPU Test Prog Director) 7.4 Test Condition B Testing o
7.4.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition B in Attachment D, EPU Test Condition Definitions.
o 7.4.2 Confirm that Shift Supervision is aware that all tests listed in Attachment E, Test Condition B Review Summary can be performed in any order at reactor power levels in the range of 3293 to 3360 MWt (83.3% to 85.0%). Reactor thermal power may briefly exceed 3360 MWt during minor power transients inherent to approved test procedures.
Confirmed By Date (Shift Supervision) 0 7.4.3 Perform tests listed in Attachment E, Test Condition B Review Summary.
7.4.4 Confirm the following:
o3
- a.
All testing listed in Attachment E, Test Condition B Review Summary has been successfully completed O.R Test Exception Reports have been written.
o]
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment E have been reviewed by the TP-199-013 Test Director or EPU Test Program Director OR Test Exception Reports have been written.
[]
- c.
All Test Exception Reports have been dispositioned.
For Information Only TP-199-013 Revision 0 Page 21 of 70 0]
- d.
There are no open Test Exceptions or Correct Condition action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition C.
/
Confirmed By (EPU Test Prog Director)
Date 13 11 7.5 Test Condition C Testing 7.5.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition B in Attachment D, EPU Test Condition Definitions.
7.5.2 Confirm that Shift Supervision is aware that all tests listed in Attachment F, Test Condition C Review Summary can be performed in any order at reactor power levels in the range of 3658 to 3733 MWt (86.5% to 94.4%) as specified in Attachment F.
Reactor thermal power may briefly exceed 3733 MWt during minor power transients inherent to approved test procedures.
/
Confirmed By (Shift Supervision)
Date CAUTION RPV Level Instrumentation and MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, power ascension shall be stopped and the issue evaluated and conveyed to the NRC prior to further power ascension. (Operating License Condition 2.C (36)(a) 5).
7.5.3 11 0
11 Perform following 94.4% vibration testing in accordance with TP-1 62-030:
- a.
Maintain reactor power between 3715 MWt and 3733 MWt (94.0% - 94.4%) as displayed on PICSY point NBA01.
- b.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
- c.
Perform Walkdown of accessible areas.
- d.
Perform Remote Walkdown of inaccessible areas.
For Information Only TP-199-013 Revision 0 Page 22 of 70
- e.
Perform MSL Strain Gauge dataset recordings:
13 (1)
Record two 3-minute segment datasets of MSL Strain Gauges.
o1 (2)
AFTER the datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
o
.(3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
- f.
Record a dataset of MSL, FW, and Extraction Steam accelerometers.
o
- g.
Record a dataset of Recirculation and RR Strain Gauges.
- h.
Inform Operations that the minimum power level of 3715 MWt is no longer in effect.
3
- i.
Evaluate dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.
Confirmed By Date (EPU Engineering) 7.5.4 LPRM Calibration ST 11 o
- a.
Request Reactor Engineering to determine if an LPRM Calibration is required during Test Condition C.
O
- b.
IF yes, THEN Perform ST 11 as listed in Attachment F.
o
- c.
IF not required, THEN Document justification for not performing ST 11 in a Test Exception Report.
o3 7.5.5 Perform remaining tests listed in Attachment F.
7.5.6 Confirm the following:
o
- a.
All testing listed in Attachment F has been successfully completed OR Test Exception Reports have been written.
For Information Only TP-1 99-013 Revision 0 Page 23 of 70 0
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment F have been reviewed by the TP-199-013 Test Director or EPU Test Program Director OR Test Exception Reports have been written.
0
- c.
All Test Exception Reports have been dispositioned.
Confirmed By Date (EPU Test Prog Director) o 7.5.7 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval.
7.6 Preparation for Power Ascension Above 3733 MWt (94.4%)
NOTE:
Steps 7.6.1 through 7.6.8 may be completed in any order.
O 7.6.1 Confirm that all CRs and CRAs necessary for power ascension above 3733 MWt (94.4%) up to a maximum of 3855 MWt (97.5%)
are resolved and Responsible Supervisor certifies that all required work is completed.
Confirmed By Date (Supervisor - Corrective Action and Assessment) o3 7.6.2 Confirm that partial closure 5 of EC 690275 has been completed.
Confirmed By Date 7.6.3 Confirm that at least 90 days have elapsed since PPL provided the NRC with the benchmark results and updated MSL limit curves identified in prerequisite 6.2.
o1
- a.
Date information was provided to NRC.
o3
- b.
Line a plus 90 days.
Confirmed By Date
For Information Only TP-199-013 Revision 0 Page 24 of 70 7.6.4 Confirm the following:
o3
- a.
There are no open Test Exceptions or Correct Condition action items related to Test Exceptions that are required to be completed and closed prior to increasing power above 3733 MWt (94.4%) to a maximum of 3855 MWt (97.5%).
o
- b.
There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition D.
Confirmed By Date (EPU Test Prog Director)
O 7.6.5 Confirm Test Plateau Review Record for the 94.4% Plateau has been approved by TRC, PORC and Plant Manager with recommendation and approval to continue power ascension to the next plateau as documented on Attachment 0.
Confirmed By Date o
7.6.6 Complete Attachment H, Unit 1 Station Verification of Activities for power ascension.
Confirmed By Date o3 7.6.7 Confirm that Reactor Engineering is aware that the initial power increase from 3733 MWt to 3855 MWt shall be made using recirculation flow along a constant rod line at an average power ascension rate not to exceed 1 %/hr.
Confirmed By Date (Reactor Engineering) 7.6.8 Obtain permission to perform following:
- a.
Increase reactor thermal power with plant conditions not to exceed 3855 MWt (97.5%) or 108 Mlbm/Hr core flow.
For Information Only TP-199-013 Revision 0 Page 25 of 70 Q
- b.
Perform all tests listed in Attachment I, Test Condition D Review Summary.
Plant Manager Date 7.7 (Start of SICTIE Section) Initial power ascension above 3733 MWt.
NOTE (1):
The initial power ascension above 3733 MWt is intended to be from 3733 MWt (94.4%) to 3855 MWt (97.5%) using reactor recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr.
NOTE (2):
BOP parameters such as main generator gross electrical output and main condenser pressure may limit reactor thermal power to a level less than 3855 MWt (97.5%).
NOTE (3):
If 3855 MWt is not achieved during the initial power ascension above 3733 MWt, subsequent power ascensions above the previous maximum power level achieved may be desired and are permissible.
NOTE (4):
Subsequent power ascensions above previous maximum power levels attained shall be done using reactor recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr. It is not necessary to use the same rod line that was used in the initial or subsequent previous power ascensions.
NOTE (5):
All testing performed during Test Condition D must be done within the range of 3779 MWt to 3855 MWt (95.6% to 97.5%) or at lower power levels as specified in Attachment I. Reactor thermal power may briefly exceed 3855 MWt during minor transients inherent to approved test procedures.
NOTE (6):
In the event acoustic signals are identified that challenge the limit curve during power ascension above 3733 MWt, dryer loads shall be evaluated and acceptance criteria be re-established based on the new data. An assessment of ACM uncertainty at the acoustic signal frequency shall be performed. (License Condition 2.C.(36) (b) 3)
For Information Only TP-199-013 Revision 0 Page 26 of 70 NOTE (7):
During power ascension above 3733 MWt, if an engineering evaluation is required because a Level 1 Acceptance Criterion was exceeded, a structural analysis to address frequency uncertainties up to +/- 10% shall be performed with assurances that peak responses that fall within this uncertainty band are addressed. (License Condition 2.C.(36) (b) 5) 7.7.1 Complete the Special, Infrequent, or Complex Test/Evolution (SICT/E) briefing using Form NDAP-QA-0320-2 AND Attach the following completed forms to this procedure:
- a.
SICT/E Briefing, Form NDAP-QA-320-2
- b.
SICT/E Roster, Form NDAP-QA-320-3 Confirmed By (Designated Activity Manager)
DDate 01 7.7.2 Inform Unit 1 Shift Supervision that the Administrative Hold Condition for exceeding 3733 MWt (prerequisite 6.4) has been lifted AND to Perform following:
- a.
Close ZWO issued in prerequisite 6.4.
- b.
Remove the Administrative Hold Condition from Unit Supervisor Turnover Sheet.
03 I
Confirmed By (Shift Supervision)
Date 7.7.3 Ensure Shift Supervision is cognizant of the Administrative Hold Condition that Reactor power may not exceed 3855 MWt (97.5%)
until this Administrative Hold Condition is lifted by this TP or as otherwise notified by the Plant Manager. Reactor thermal power may briefly exceed 3855 MWt during minor power transients inherent to approved test procedures.
Confirmed By Date
For Information Only TP-1 99-013 Revision 0 Page 27 of 70 Confirm that Shift Supervision is aware that all tests listed in Attachment I, Test Condition D Review Summary can be performed in any order at reactor power levels in the range of 3779 to 3855 MWt (95.6% to 97.5%) or at lower power levels as specified in Attachment I.
0 7.7.4
/
Confirmed By (Shift Supervision)
Date CAUTION (1)
If any frequency peaks from MSL Strain Gauge data exceed limit curves above 3733 MWt, Reactor Power shall be returned to a power level at which the acceptance criteria is not exceeded. (Operating License Condition 2.C.(36) (a) 4).
CAUTION (2)
RPV Level Instrumentation and MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels In proportion to instrumentation data, power ascension shall be stopped and the issue evaluated and conveyed to the NRC prior to further power ascension. (Operating License Condition 2.C(36)(a) 5).
0 7.7.5 Inform Test Director for TP-162-030, Steam Dryer and Flow Induced Vibration Testing that the initial power ascension from 3733 MWt (94.4%) to 3855 MWt (97.5%) is about to commence AND Confirm that all test personnel are in place and prepared to perform assigned duties.
I Confirmed By Date
ýor Information Only TP-1 99-013 Revision 0 Page 28 of 70 NOTE:
All thermal power ascension ramps above previously attained thermal power levels must meet the following requirements:
SICTIE Controls must be established in accordance with NDAP-QA-0320 TP-162-030 and OI-TA-008 test personnel must be in place and ready to monitor and record data 0
Power ascension ramps are limited to less than or equal to 1% 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0
Power ascension ramps are to utilize Reactor Recirculation flow only Vibration datasets during power increases are collected but not analyzed and inserted into the Test Point Report. Datasets are analyzed at each 3.5% plateau. (Operating License Condition 2.C(36)(a) 3) 7.7.6 Complete ramp to 3855 MWt (97.5%) as follows:
o
- a.
Complete Attachment J, EPU Test Program Power Ramp Data items recorded prior to start of ramp step.
o
- b.
Inform Shift Supervision to perform a power increase step not to exceed 1% per hour increase in reactor power.
o
- c.
Complete Attachment J items recorded for the power ramp step.
- d.
AFTER the power ramp step has been completed, THEN Inform TP-1 62-030 Test Director to perform following (in any order):
o (1) Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
o (2)
Record a dataset of MSL Strain Gauges.
o (3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
(4)
Record a dataset of MSL, FW, and Extraction Steam accelerometers.
For Information Only TP-199-013 Revision 0 Page 29 of 70 o
(5)
Record a dataset of Recirculation and RHR Strain Gauges O3 (6)
Record a dataset for OI-TA-008 Data Acquisition o
(7)
Perform Walkdown of accessible areas.
o (8)
Perform Remote Walkdown of inaccessible areas.
o
- e.
Repeat Steps 7.7.6.a - d above when directed by Reactor Engineering until 3855 MWt is achieved.
NOTE:
After the plant has reached a stable steady state power level of 3855 MWT (97.5%) the SICTIE for this plateau is terminated.
7.8 Test Condition D Testing o
7.8.1 Perform testing listed in Attachment I, Test Condition Review Summary while completing the remaining steps in this section.
7.8.2 Perform following 97.5% vibration testing in accordance with TP-162-030:
o
- a.
Maintain reactor power between 3837 MWt and 3855 MWt (97% - 97.5%) as displayed on PICSY point NBA01.
o
- b.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
ol
- c.
Perform Walkdown of accessible areas.
o
- d.
Perform Remote Walkdown of inaccessible areas.
- e.
Perform MSL Strain Gauge dataset recordings:
o (1) Record two 3-minute segment datasets of MSL Strain Gauges.
o (2)
AFTER the datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
o3 (3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
For Information Only TP-199-013 Revision 0 Page 30 of 70 o3
- f.
Record a dataset of MSL, FW, and Extraction Steam accelerometers.
o
- g.
Record a dataset of Recirculation and RR Strain Gauges.
O
- h.
Record a dataset for OI-TA-008 Data Acquisition.
o
- i.
inform Operations that the minimum power level of 3837 MWt is no longer in effect.
o j
Perform an evaluation of the recorded dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.
Confirmed By Date (EPU Engineering) o
- k. Confirm that it is acceptable to proceed to the next vibration testing test point.
Confirmed By Date (EPU Engineering) o 7.8.3 Prepare a steam dryer performance evaluation for 3855 MWt as required by License Condition 2.C.(36)(a)3.
n 7.8.4 Record date and time that information was provided to the NRC Project Manager.
Date Time Confirmed By Date 7.8.5 Confirm the following:
O
- a.
All testing listed in Attachment I has been successfully completed OR Test Exception Reports have been written.
O
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment I have been reviewed by the TP-1 99-013 Test Director or EPU Test Program Director OR Test Exception Reports have been written.
For Information Only TP-199-013 Revision 0 Page 31 of 70
- c.
All Test Exception Reports have been dispositioned.
01 I
Confirmed By (EPU Test Prog Director)
Date 0]
7.8.6 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval.
7.9 Preparation for Power Ascension Above 3855 MWt (97.5%)
NOTE:
Steps 7.9.1 through 7.9.6 may be completed in any order.
[]
7.9.1 Confirm that all CRs and CRAs necessary for power ascension above 3855 MWt (97.5%) are resolved and Responsible Supervisor certifies that all required work is completed.
/
Confirmed By (Manager - Corrective Action and Assessment)
Date 7.9.2 Confirm that at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> have elapsed since the NRC Project Manager confirmed receipt of the steam dryer performance evaluation for 3855 MWt as required by License Condition 2.C.(36)(a)3.
0 01
- a.
Date and time that NRC Project Manager confirmed receipt of information
- b.
Line a plus 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.
- c.
Date and time this step is signed off (2! line b).
Date Time Date Time Date Time Confirmed By
For Information Only TP-1 99-013 Revision 0 Page 32 of 70 7.9.3 Confirm the following:
- a.
There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to increasing power above 3855 MWt (97.5%).
O
- b.
There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition E.
Confirmed By Date (EPU Test Prog Director)
O 7.9.4 Confirm Test Plateau Review Record for the 97.5% Plateau has been approved by TRC, PORC and Plant Manager with recommendation and approval to continue power ascension to the next plateau as documented on Attachment 0.
Confirmed By Date O]
7.9.5 Complete Attachment H, "Unit 1 Station Verification of Activities for Power Ascension".
o1 7.9.6 Confirm that Reactor Engineering is aware that the initial power increase from 3855 MWt to 3952 MWt shall be made using recirculation flow along a constant rod line at an average rate not to exceed 1%/hr.
Confirmed By Date (Reactor Engineering) 7.9.7 Obtain permission to perform following:
O3
- a.
Increase reactor thermal power with plant conditions not to exceed 3952 MWt (100%) or 108 Mlbm/Hr core flow.
O
- b.
Perform all tests listed in Attachment K.
Plant Manager Date
For Information Only TP-1 99-013 Revision 0 Page 33 of 70 7.10 (Start of SICT/E Section) Initial power ascension above 3855 MWt (97.5%).
NOTE (1):
The initial power ascension above 3855 MWt is intended to be from 3855 (97.5%) to 3952 MWt (100%) using reactor recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr.
NOTE (2):
BOP parameters such as main generator gross electrical output and main condenser pressure will most likely limit reactor thermal power to a level less than 3952 MWt (100%).
NOTE (3):
If 3952 MWt is not achieved during the initial power ascension above 3855 MWt, subsequent power ascensions above the previous maximum power achieved may be desired and are permissible.
NOTE (4):
Subsequent power ascensions above previous maximum power levels attained shall be done using reactor recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr. It is not necessary to use the same rod line that was used in the initial or subsequent previous power ascensions.
NOTE (5):
All testing performed during Test Condition E must be done within the range of 3873 MWt to 3952 MWt (98.0% to 100%) or at lower power levels as specified in Attachment K.
NOTE (6):
in the event acoustic signals are identified that challenge the limit curve during power ascension above 3733 MWt, dryer loads shall be evaluated and acceptance criteria be re-established based on the new data. An assessment of ACM uncertainty at the acoustic signal frequency shall be performed. (License Condition 2.C.(36) (b) 3)
NOTE (7)
During power ascension above 3733 MWt, if an engineering evaluation is required because a Level 1 Acceptance Criterion was exceeded, a structural analysis to address frequency uncertainties up to +/- 10% shall be performed with assurances that peak responses that fall within this uncertainty band are addressed. (License Condition 2.C.(36) (b) 5).
7.10.1 Complete the Special, Infrequent, or Complex Test/Evolution (SICT/E) briefing using Form NDAP-QA-0320-2 AND Attach the following completed forms to this procedure:
13
- a.
SICT/E Briefing, Form NDAP-QA-320-2
For Information Only TP-1 99-013 Revision 0 Page 34 of 70 o
- b.
SICT/E Roster, Form NDAP-QA-320-3 Confirmed By Date (Designated Activity Manager)
O 7.10.2 Inform Unit 1 Shift Supervision that the Administrative Hold Condition for exceeding 3855 MWt (Prerequisite 6.5) has been lifted AND to Perform following:
o
- a.
Close ZWO issued in Prerequisite 6.5.
o3
- b.
Remove the Administrative Hold Condition from Unit Supervisor Turnover Sheet.
Confirmed By Date (Shift Supervision) o3 7.10.3 Confirm that Shift Supervision is aware that all tests listed in Attachment K, Test Condition E Review Summary can be performed in any order at reactor power levels in the range of 3873 to 3952 MWt (98.0% to 100%) or at lower power levels as specified in Attachment K.
Confirmed By Date (Shift Supervision)
For Information Only TP-1 99-013 Revision 0 Page 35 of 70 CAUTION (1)
If any frequency peaks from MSL Strain Gauge data exceed limit curves above 3733 MWt, Reactor Power shall be returned to a power level at which the acceptance criteria is not exceeded. (Operating License Condition 2.C.(36) (a) 4).
CAUTION (2)
RPV Level Instrumentation and MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, power ascension shall be stopped and the issue evaluated and conveyed to the NRC prior to further power ascension. (Operating License Condition 2.C(36)(a) 5).
13 7.10.4 Inform Test Director for TP-1 62-030, Steam Dryer and Flow Induced Vibration Testing that the initial power ascension from 3855 MWt (97.5%) to 3952 MWt (100%) is about to commence AND Confirm that all test personnel are in place and prepared to perform assigned duties.
I Confirmed By Date
For Information Only TP-199-013 Revision 0 Page 36 of 70 NOTE:
All thermal power ascension ramps above previously attained thermal power levels must meet the following requirements:
SICT/E Controls must be established in accordance with NDAP-QA-0320 TP-162-030 and OI-TA-008 test personnel must be in place and ready to monitor and record data Power ascension ramps are limited to less than or equal to 1% / hour Power ascension ramps are to utilize Reactor Recirculation flow only Vibration datasets during power increases are collected but not analyzed and inserted into the Test Point Report. Datasets are analyzed at each 3.5% plateau. (Operating License Condition 2.C(36)(a) 3) 7.10.5 Complete ramp to 3952 MWt (100%) as follows:
11 13 0l
- a.
Complete Attachment J, EPU Test Program Power Ramp Data items recorded prior to start of ramp step.
- b.
Inform Shift Supervision to perform a power increase step not to exceed 1% per hour increase in reactor power.
- c.
Complete Attachment J items recorded for the power ramp step.
- d.
ONCE the power ramp step has been completed, THEN Inform TP-162-030 Test Director to perform following (in any order):
(1)
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
(2)
Record a dataset of MSL Strain Gauges.
(3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
(4)
Record a dataset of MSL, 'W, and Extraction Steam accelerometers.
0 0
03
For Information Only TP-199-013 Revision 0 Page 37 of 70 Q
(5)
Record a dataset of Recirculation and RHR Strain Gauges o
(6)
Record a dataset for OI-TA-008 Data Acquisition o
(7)
Perform Walkdown of accessible areas.
o (8)
Perform Remote Walkdown of inaccessible areas.
- e.
Repeat steps 7.10.5.a - d above when directed by Reactor Engineering until one of the following occurs:
o (1) 3952 MWt is achieved OR o
(2)
BOP parameters such as main generator gross electrical output and main condenser pressure limit(s) are reached.
Q3
- f.
Record date and time when 3872 MWt (98.0%) was initiall achieved.
DATE TIME o
- g.
Record date and time when 3952 MWt (100%) OR highest power level was initiall achieved.
MWt DATE TIME (NBA01)
NOTE:
After the plant has reached a stable steady state power level of 3952 MWt (100%) or the highest power level achievable, the SICT/E for this plateau is terminated.
For Information Only TP-199-013 Revision 0 Page 38 of 70 7.11 Test Condition E Testing NOTE:
TC E is defined as 3873 MWt to 3952 MWt (98% -100%). If 3952 MWt is not achievable, required testing specified to be performed at 3952 MWt is to be performed in the band between highest power level achievable minus 18 MWt. Testing not identified to be performed at a specific power level can be performed in any order and within 3873 MWt to 3952 MWt as identified on Attachment K.
7.11.1 Perform following 100% vibration testing in accordance with TP-1 62-030:
o
- a.
Maintain reactor power between 3934 MWt and 3952 MWt (99.5% - 100%) OR highest achievable power minus 18 MWt as displayed on PICSY point NBA01.
o
- b.
IF initial 100% power level was achieved with core flow between 100 Mlb/Hr and 101 Mlbm/Hr THEN Maintain core flow between 100 Mlbm/Hr and 101 Mlbm/Hr.
Otherwise this step is N/A.
o
- c.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
o3
- d.
Perform Walkdown of accessible areas.
0
- e.
Perform Remote Walkdown of inaccessible areas.
- f.
Perform MSL Strain Gauge dataset recordings:
o (1) Record two 3-minute segment datasets of MSL Strain Gauges.
o3 (2)
AFTER the datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
[
(3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
o
- g.
Record a dataset of MSL, FW, and Extraction Steam accelerometers.
13
- h.
Record a dataset of Recirculation and RR Strain Gauges.
For Information Only TP-1 99-013 Revision 0 Page 39 of 70 Q
7.11.2 Perform remaining testing identified on Attachment K, Test Condition E Review Summary not requiring specific core flow or power level.
NOTE:
Sections 7.12 and 7.13 can be performed in either order.
7.12 TC E Testing at 100 MIb/Hr Core Flow NOTE:
If core flow was established between 100 Mlbm/Hr and 101 Mlbm/Hr supporting section 7.11 vibration testing, then section 7.12 can be NIA'd with documentation as to why this section is not applicable on Attachment A, Test Documentation.
7.12.1 Establish core flow between 100 and 101 Mlbm/Hr (100.5 t.5 Mlbm/Hr).
7.12.2 Perform following 100 Mlb/Hr vibration testing in accordance with TP-162-030:
o
- a.
Maintain core flow between 100 and 101 Mlb/Hr until all vibration datasets have been completed.
o
- b.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
- c.
Perform MSL Strain Gauge dataset recordings:
o (1) Record two 3-minute segment datasets of MSL Strain Gauges.
o (2)
AFTER the datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
(3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
o
- d.
Record a dataset of MSL, FW, Recirc, RHR and Extraction Steam accelerometers.
o
- e.
Record a dataset of Recirculation and RR Strain Gauges.
[]
- f.
Inform Operations that the restrictions on core flow is no longer in effect.
For Information Only TP-1 99-013 Revision 0 Page 40 of 70 7.12.3 Perform ST-1 B, Moisture Carryover by completing Attachment G, Moisture Carryover Support Data.
7.13 TC E Testing at 108 Mlb/Hr Core Flow 7.13.1 Establish core flow between 107 and 108 Mlbm/Hr.
7.13.2 Perform following 108 MIb/Hr vibration testing in accordance with TP-1 62-030:
O
- a.
Maintain core flow between 107 and 108 MIb/Hr until all vibration datasets have been completed.
o
- b.
Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.
- c.
Perform MSL Strain Gauge dataset recordings:
o (1) Record two 3-minute segment datasets of MSL Strain Gauges.
o (2)
AFTER the datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.
o (3)
Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.
Q
- d.
Record a dataset of MSL, FW, Recirc, RHR and Extraction Steam accelerometers.
o3
- e.
Record a dataset of Recirculation and RHR Strain Gauges.
o
- f.
Inform Operations that the restrictions on core flow is no longer in effect.
Q3 7.13.3 Perform ST-B, Moisture Carryover by completing Attachment G, Moisture Carryover Support Data.
7.14 Test Condition E Review 7.14.1 Confirm the following:
O
- a.
All testing listed in Attachment K has been successfully completed OR Test Exception Reports have been written.
Information Only TP-199-013 Revision 0 Page 41 of 70 o
- b.
All EPU Test Results Summaries for completed Startup Tests listed in Attachment K have been reviewed by the Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written.
o
- c.
All Test Exception Reports have been dispositioned.
Confirmed By Date O
7.14.2 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC, and Plant Manager for review and approval.
Confirmed By Date O]
7.14.3 Prepare a steam dryer performance evaluation for 3952 MWt as required by License Condition 2.C.(20)(a)3.
o1 7.14.4 Record date and time that the steam dryer performance evaluation for 3952 MWt was provided to the NRC Project Manager.
Date Time Confirmed By Date
- 8.
RESTORATION 8.1 Confirm Test Plateau Review Record for the 100% Plateau has been approved by TRC, PORC and Plant Manager as documented on Attachment 0.
Confirmed By Date 8.2 Prepare a Final Test Program Review Record, Attachment Q, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval.
For Information Only TP-199-013 Revision 0 Page 42 of 70 8.3 Confirm that the Final Test Program Review has been approved.
Confirmed By Date (EPU Test Prog Director)
- 9.
ACCEPTANCE CRITERIA There are no specific Acceptance Criteria associated with this test.
- 10.
REVIEW 10.1 Review of this procedure is complete.
Confirmed By Date
- 11.
RECORDS 11.1 The original completed test procedure shall be transmitted to DCS.
11.2 The completed test procedure includes the attached forms identified below as well as procedure attachments:
11.2.1 SICT/E Analysis, Form NDAP-QA-0320-1 11.2.2 SICT/E Briefing, Form NDAP-QA-0320-2 11.2.3 SICT/E Roster, Form NDAP-QA-0320-3 Confirmed By Date
For Information Only Attachment A TP-199-013 Revision 0 Page 43 of 70 TEST CONTROL DOCUMENTATION Procedure No. TP-199-013 Page of Page 1 of 1
For Information Only Attachment B TP-199-013 Revision 0 Page 44 of 70 EPU TEST 42 Required Surveillances Confirm that the following procedures have been successfully completed:
SI-183-304, 24 Month Calibration of Main Steam Line A Flow Channels FIS-B21-1N006A&B and Main Steam Line B Flow Channels FIS-B21-1N007A&B 1016661 SI-183-305, 24 Month Calibration of Main Steam Line A Flow Channels FIS-B21-1N006C&D and Main Steam Line B Flow Channels FIS-B21-1N007C&D 1178054 SI-183-306, 24 Month Calibration of Main Steam Line C Flow Channels FIS-B21-1N008C&D and Main Steam Line D Flow Channels FIS-B21-1N009C&D 1021572 SI-183-307, 24 Month Calibration of Main Steam Line C Flow Channels FIS-B21-1N008A&B and Main Steam Line D Flow Channels FIS-B21-1N009A&B 1016662,1186039
/
Confirmed By Date Page 1 of 1
Attachment C TP-1 99-013 Revision 0 Page 45 of 70 0
0
-h 0
I'-1 o
ýs 0-0<
Test Condition A Review Summary TP-199-013 Additional Plant Procedure Description Test Results Subtest Conditions Number TetSummary All TERs Completed Reviewed Dispositioned Number Requirements (Initial/Date)
(Initial/Date)
(Initial/Date) 3 5.1 12B 42 10.1 5.2 4
22.1 22.2 22.3 22.1 Mode 5 Mode 5 or Mode 4 Mode 5 or Mode 4 Mode 5 or Mode 4 Mode 5 or Mode 4 Mode 4 AND/OR
< 1580 MWt (40%)
Mode 2
- Every 120 MWt (3%) following gen sync up to 60%
-1027 MWt (26%)
-2569 MWt (60%)
- Every 120 MWt (3%) from 60% to 83.3%
-3293 MWt (65%)
RE-081-036 TP-055-001 TP-199-013 Attachment L TP-199-013 Attachment B TP-199-013 Attachment T SR-155-004 SR-100-008 TP-193-041 TP-199-013 Attachment V TP-193-041 TP-199-013 Attachment V TP-193-041 TP-199-013 Attachment V TP-193-041 TP-199-013 Attachment V TP-162-030 (83.3%)
Core Fuel Pool Verification CRD Stroke Time RBM Calibration I&C Surveillances IRM Surveillances Scram Time Measurements of Control Rods In Sequence Critical and Shutdown Margin Demo.
Pressure Regulator Incremental Regulation Scram Bypass Setpoint Verification Pressure Regulator Step Changes and Pressure Regulator Failure Pressure Regulator Incremental Regulation Steam Dryer Steady State Vibration Data and Plant Walkdown 100,33 Page 1 of 2
Attachment C TP-199-013 Revision 0 Page 46 of 70 Test Condition A Review Summary TP-199-013 Additional Plant Procedure Description Results Subtest Conditions Number Test Summary All TERs Completed Reviewed Dispositioned Number Requirements (Initial/Date)
(Initial/Date)
(Initial/Date) 11 Per Station SR-178-012 LPRM Calibration Schedule 12A.2 Per Station TP-199-013 APRM Calibration Schedule Attachment M 10.2 When switching GO-100-004 IRM/APRM Overlap from Mode 1 to 2
- Fij 0
0 F1 Ct 0
0
'I Page 2 of 2
For Information Only Attachment D TP-199-013 Revision 0 Page 47 of 70 EPU Test Condition Definitions 120 110 120 PURPOSE: Not For Control Room Use EPU TAqt Condition Dafinitions Onlv lin
- STABILIlY REGION I IF OPRM INOPERABLE IMMEDIATE 100 SCRAM LAW ON-176-oo2 IF OPRM OPERABLE IMMEDIATE EXIT lAW ON178-0,2 n
f-r-rL-APRMRod Bloc LL1j MELLLA i
B undary I
f r 7 90 Iy REGION JTELY EXIT lAW ON-1711-002 It" 90 80 It
'ES1MICTEn REGION ka defined In Attachm-nt G to IDAP-GA-0338)
F ABOVE MELLLA BOUNDARY, MMEDIATELY EXIT LAW ON-178-02 L
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10 20 30 40 50 60 70 80 90 100 Total Core Flow (Mlbmlhr)
Not For Control Room Use - Info Only Page 1 of 1
Attachment E TP-199-013 Revision 0 Page 48 of 70 0
H H,
0 0
k<
Test Condition B Review Summary TP-199-013 Additional Plant Procedure Description Subtest Conditions Number Number Requirements 101 TP-100-013 Baseline Data Collection & Extrapolal 12A.2 TP-199-013 APRM Calibration Attachment M 19 TP-199-"13 Core Thermal Limits Attachment N 22.1
~ Every 120 MWt TP-193-041 Pressure Regulator Incremental Reg*
(3%)
TP-199-013 Attachment V 22.3 3360 MWt (85%)
TP-193-041 Pressure Regulator Step Changes TP-199-013 Attachment V 23 TP-145-029 Feedwater Level Setpoint Changes 24 3360 MWt (85%)
TP-193-041 Turbine Valve Surveillance TP-199-013 Attachment W Test Completed (Initial/Date) ton ilation Test Completed (lnitiallDate)
Results Summary Reviewed (Initial/Date)
Results Summary Reviewed Ilnitial/Date)
All TERs Dispositioned (IniUal/Date)
All TERs Dispositioned (Initial/Date)_
Page 1 of 1
Attachment F TP-199-013 Revision 0 Page 49 of 70 0
0
'-1 Test Condition C Review Summary TP-199-013 Additional Plant Procedure Description Results Subes Cndtios umerTest Summary All TERs Subtest Conditions Number Completed Reviewed Dispositioned Number Requirements (Initial/Date)
(Initial/Date)
(Initial/Date) 100 3293 MWt (83.3%)
TP-162-030 Steam Dryer Steady State Vibration Data and Plant Walkdown 100 3733 MWt (94.4%)
TP-162-030 Steam Dryer Steady State Vibration Data and Plant Walkdown 101 TP-100-013 Baseline Data Collection & Extrapolation 103 TP-144-048 Condensate Pump Trip 11 SR-1 78-012 LPRM Calibration 12A.2 3733 MWt (94.4%)
TP-199-013 APRM Calibration Attachment M 19 TP-199-013 Core Thermal Limits Attachment N 1A TP-199-013 Chemical and Radiochemical Attachment S 1B TP-199-013 Moisture Carryover Attachment G
- 2.
TP-199-013 Radiation Measurements Attachment U 22.1
- Every 120 MWt TP-193-041 Pressure Regulator Incremental Regulation (3%)
TP-199-013 Attachment V 22.3 3733 MWt (94.4%)
TP-1 93-041 Pressure Regulator Step Changes and TP-199-013 Pressure Regulator Failure Attachment V 23 TP-045-001 Feedwater Level Setpoint Changes 24 3733 MWt (94.4%)
TP-199-013 Turbine Valve Surveillance Attachment W TP-193-041 32 SO-100-007 Drywell Cooling Attachment A Item 9 0
Page 1 of 1
r or Information Only Attachment G TP-199-013 Revision 0 Page 50 of 70 ST IB Moisture Carryover Testing Test Condition Core Flow Completion of the following steps satisfies the requirement of ST 1 B:
- 1.
Instruct Chemistry to perform CH-SY-026 "Moisture Carry Over."
- 2.
Attach copy of Core Performance Verification Printouts created during performance of ST-19 at same power/flow conditions.
- 3.
Record plant data listed in table below using specified PICSY points.
- 4.
Inform TP-199-013 Test Director when sample has been collected.
- 5.
Record Main Steam Line moisture content:
- 6.
Verify Main Steam Line moisture content is not in excess of 0.1 wt% (Level 2 Acceptance Criterion)
Verified By Date
.Parameter PICSY Point Value Reactor Water Level NFLOI NFL02 NFL03 MSL Flow NFF01 NFF02 NFF03 NFF04 Total Feedwater flow FPA10 (Mlb/hr) 10 minute average CRD flow (Mlblhr)
NEF52 Reactor Power NBA01 Page 1 of 1
Lor Information Only Attachment H TP-199-013 Revision 0 Page 51 of 70 Unit I Station Verification of Activities for Power Ascension All action items required for power ascension above the current maximum power level of MWt for which my group is responsible have been completed.
Manager - Nuclear Operations Manager - Nuclear Maintenance Supervisor - Reactor Engineering Supervisor - Health Physics Supervisor - Chemistry Manager - Nuclear Systems Engineering Manager - Special Projects I
Page 1 of 1
Attachment I TP-199-013 Revision 0 Page 52 of 70 0
H, I-h 0
Ct.
0 0
o1 Test Condition D Review Summary TP-199-013 Additional Plant Procedure Description Results Subtest Conditions Number Test Summary All TERs Completed Reviewed Dispositioned Number Requirements (Initial/Date)
(Initial/Date)
(Initial/Date) 100.PA Initial ascension to TP-162-030 Steam Dryer Vibe Monitoring During 3855 MWt (97.5%)
Ascension 100.SSW 3855 MWt (97.5%)
TP-162-030 Steam Dryer Steady State Vibration Data and Plant Walkdown 101 TP-100-013 Baseline Data Collection & Extrapolation 12A.2 TP-199-013 APRM Calibration Attachment M 19 TP-199-013 Core Thermal Limits Attachment N 22.1
~ Every 120 MWt TP-199-013 Pressure Regulator Incremental Regulation (3%)
Attachment V TP-193-041 22.3 3855 MWt (97.5%)
TP-193-041 Pressure Regulator Step Changes 23 TP-145-029 Feedwater Level Setpoint Changes 24 3855 MWt (97.5%)
TP-199-013 Turbine Valve Surveillance Attachment W TP-193-041 1B TP-199-013 Moisture Carryover Attachment G Page 1 of 1
Attachment J TP-199-013 Revision 0 Page 53 of 70 I-h H-0*
0 EPU Test Program Power Ramp Data Date SICTIE Control In Effect Testing Personnel Ready Prior to Ramp - MWt Prior to Ramp - Gross MWe Prior to Ramp - MVAR Notified Shift Supervision Time at Start of Ramp Time at End of Ramp Post Ramp - MWt Post Ramp - Gross MWe Post Ramp - MVAR Sheet of Page 1 of 1
Attachment K TP-1 99-01"3 Revision 0 Page 54 of 70 0
H 1h 0
Cr 0
0 Test Condition E Review Summary i
w, I"Results TP-199-013 Additional Plant Procedure Description Test Summary All TERs Subtest Conditions Number Completed Reviewed Dispositioned Number Requirements (Initial/Date)
(Initial/Date)
(Initial/Date) 100 100 101 103 11 12A.2 12A.3 19 1A 1B 1B 2
22.1 Initial ascension to 3952 MWt (100%)
3952 MWt (100%)
Note 1 3952 MWt (100%)
TP-164-031 performed first 100 MIb/Hr 108 Mlb/Hr
- Every 120 MWt (3%)
TP-162-030 TP-162-030 TP-100-013 TP-144-048 SR-178-012 TP-199-013 Attachment M SE-1 78-001(2)(3)(4)
TP-199-013 Attachment N TP-199-013 Attachment S TP-199-013 Attachment G TP-199-013 Attachment G TP-199-013 Attachment U TP-1 93-041 TP-199-013 Attachment V Steam Dryer Vibe Monitoring During Ascension Steam Dryer Steady State Vibration Data and Plant Walkdown Baseline Data Collection & Extrapolation Condensate Pump Trip LPRM Calibration APRM Calibration APRM 11(12)(13)(14) Drive Flow Calibration Core Thermal Limits Chemical and Radiochemical Moisture Carryover Moisture Carryover Radiation Measurements Pressure Regulator Incremental Regulation Page 1 of 2
Attachment K TP-1 99-013 Revision 0 Page 55 of 70 0
H t-h 0
rr F-o 0
Test Condition E Review Summary TP-199-013 Additional Plant Procedure Description Results Subtest Conditions Number Test Summary All TERs Completed Reviewed Dispositioned Number Requirements (InitiaVDate)
(initial/Date)
(InitialJDate) 22.5 TP-193-041 SLRC and Incremental Regulation TP-199-013 Evaluation, Load Limit Potentiometer Attachment V Check 32 SO-100-007 Drywell Cooling Attachment A Item 9 35 3952 MWt (100%)
TP-164-031 Core Flow Calibration 100 MIb/Hr 18 RE-0TP-201 TIP Uncertainty 29.2 SE-164-305 Recirc M-G Set Positioners High Speed Stops 36 TP-1 99-010 EPU Temperature Data Collection for Service Water 49 SI-179-360 MSL Rad Monitor Adjustment Note 1 Test 103 required by M-1563 and License Condition 2.c.(37)(b). Relief to not perform test if performed successfully at 3733 MWt granted by NRC Letter 2009-0052.
Page 2 of 2
For Information Only Attachment L TP-199-013 Revision 0 Page 56 of 70 ST 12B RBM TESTING Completion of the following steps satisfies the requirement for ST 12B testing:
- 1. Level 1 Acceptance Criterion a, test 12B. Confirm that the RBM setpoints reflect the appropriate EPU settings.
- 2. Level 1 Acceptance Criterion b, test 12B. Confirm that the RBM setpoints enable at the proper power levels for EPU settings.
Confirmed By Date Station Engineering Page I of 1
or Information Only Attachment M TP-199-013 Revision 0 Page 57 of 70 ST 12A APRM TESTING Completion of the following steps satisfies the requirement for ST 12A testing:
- 2. Perform SO-1 78-004.
S3.
Level I Acceptance Criterion a, test 12A. Confirm that the APRM system is calibrated consistent with Technical Specifications.
- 4. Level I Acceptance Criterion b, test 12A. Confirm that Technical Specifications on APRM scram and rod block setpoints are not being exceeded.
Confirmed By Date Station Engineering Page 1 of 1
for Information Only Attachment N TP-199-013 Revision 0 Page 58 of 70 ST-19 CORE PERFORMANCE Enter Test Condition Completion of the following steps satisfies the requirements for MELLLA ST 19.
- 1. Obtain and Attach copy of SO-1 00-007, Attachment A, Item 11.
__ 2. Level 1 Acceptance Criterion a, test 19. Confirm that core thermal limits CMPRAT, CMFLCPR and CMFDLRX are less than 1.0. Refer to SO-100-007 item 11.
- 3. Level i Acceptance Criterion b, test 19. Confirm that steady state reactor power is limited to the maximum value of the lesser of either 3952 MWt or the MELLLA Boundary as depicted on the Power / Flow map.
_4.
Level I Acceptance Criterion c, test 19. Confirm that core flow does not exceed its maximum and minimum values as depicted on the Power / Flow map.
__ 5. Obtain and Attach Core Performance Verification printouts from Reactor Engineering.
Confirmed By Date Station Engineering Page 1 of 1
or Information Only TP-199-013 Revision 0 Page 59 of 70 TEST PLATEAU REVIEW RECORD
- 1. Identify current Test Plateau:
- 2. List all tests scheduled for this current Test Plateau which were not completed to the extent required and the related Test Exception Reports.
- 3. List all tests completed during the current Test Plateau for which EPU Test Results Summaries have not been reviewed and the related Test Exception Reports.
- 4. List all Test Exception Reports which remain open.
SUMMARY
All testing scheduled for the current Test Plateau has been successfully completed to the extent required, including related analysis, and EPU Test Results Summaries have been reviewed with the exception of the open items listed above. All Test Exception Reports have been resolved. The open items list can be carried without impacting the safe operation of the plant.
Test Plateau Review completed and recommended for approval:
I EPU Test Program Director Date TRC Meeting:
/
PORC Meeting:
/
Test Plateau Review Approved:
Plant Manager Date Page 1 of 1
or Information Only Attachment P TP-199-013 Revision 0 Page 60 of 70 Page intentionally left Blank Page 1 of 1
For Information Only Attachment Q TP-1 99-013 Revision 0 Page 61 of 70 FINAL TEST PROGRAM REVIEW RECORD
- 1. List all tests scheduled for the EPU Test Program which were not completed to the extent required and the related Test Exception Reports.
- 2. List all tests completed during the EPU Test Program for which EPU Test Results Summaries have not been reviewed and the related Test Exception Reports.
- 3. List all Test Exception Reports which remain open.
SUMMARY
All testing scheduled for the EPU Test Program has been successfully completed to the extent required, including related analysis, and EPU Test Results Summaries have been reviewed with the exception of the open items listed above. All Test Exception Reports have been resolved. The open items list can be carried without impacting the safe operation of the plant.
Test Plateau Review completed and recommended for approval:
EPU Test Program Director
/
Date TRC Meeting:
/
PORC Meeting:
/
Test Plateau Review Approved:
I Plant Manager Date Page 1 of 1
For Information Only Attachment R TP-199-013 Revision 0 Page 62 of 70 TP-199-013 SUBTEST NUMBERS TP-199-013 M-1563 Subtest Number Number Description or Title Implementing Procedure Number 1
1A 1
1B 2
2 3
4 5
5 10 11 12 12 3
4 5.1 5.2 10 11 12A. 1 12A.2 Chemical and Radiochemical Moisture Carryover Radiological Survey Program in Support of the Unit 1 EPU Modification Core Fuel Pool Verification In Sequence Critical and Shutdown Margin Demo.
CRD Stroke Time Scram Time Measurements of Control Rods IRM/APRM Overlap LPRM Calibration Validation of Core Thermal Power Heat Balance APRM Calibration APRM 11(12)(13)(14) Drive Flow Calibration RBM Calibration TIP Uncertainty Core Thermal Limits Pressure Regulator Incremental Regulation Scram Bypass Setpoint Verification TP-199-013 Attachment S TP-1 99-013 Attachment G HP-TP-521 RE-081-036 SR-100-008 TP-055-001 SR-155-004 GO-100-004 SR-178-012 RE-1 TP-026 TP-1 99-013 Attachment P SE-178-001 (2)(3)(4)
TP-199-013 Attachment L RE-OTP-201 TP-199-013 Attachment N TP-1 93-041 TP-1 93-041 12 12A.3 12 12B 18 19 22 22 18 19 22.1 22.2 Page 1 of 2
Information Only Attachment R TP-199-013 Revision 0 Page 63 of 70 Implementing Description or Procedure Title Number TP-199-013 M-1563 Subtest Number Number 22 22 23 24 29 32 33 35 36 37 22.3 22.4 23 24 29.2 32 NA 35 36 37 Pressure Regulator Step Changes and Ctrl Failures SLRC Eval and Incremental Regulation Evaluation Feedwater Master Water Level Controller Tuneup Turbine Valve Surveillance Recirc MG Set Positioners High Speed Stops Drywell Cooling (Combined into ST 100)
Core Flow Calibration EPU Temperature Data Collection for Service Water Gaseous Radwaste Systems (Combined with ST 1A)
I&C Surveillances MSL Rad Monitor Adjustment Steam Dryer Steady State Vibration Data Steam Dryer Vibe Monitoring During Ascension Plant Walkdown Baseline Data Collection & Extrapolation Condensate Pump Trip TP-1 93-041 TP-1 93-041 TP-145-029 TP-193-041 SE-164-305 SO-100-007 Attachment A Item 9 TP-164-031 TP-1 99-997 TP-199-013 Attachment S TP-199-013 Attachment B SI-179-360 TP-1 62-030 TP-162-030 TP-162-030 TP-100-013 TP-1 44-048 42 42 49 100 100 100 101 103 49 100.1 100.3 100.4 101 103 Page 2 of 2
Information Only Attachment S TP-199-013 Revision 0 Page 64 of 70 ST-1A CHEMICAL AND RADIOCHEMICAL (Includes ST 37 Gaseous Radwaste)
Enter Test Condition Completion of the following steps satisfies the requirements for ST 1A and 37.
- 1. Confirm that samples have been taken for the following procedures:
- a.
- b.
SC-1 76-102
- c.
SC-1 76-106
- d.
- e.
- f.
- 3. Confirm completion of analysis for the samples collected in step 1.
_4.
IF a Radwaste discharge has been completed since the last power increase, THEN Confirm completion of SC-069-001. OTHERWISE, N/A this step.
_5.
Confirm that the following Level 1 Acceptance Criterion is satisfied: Chemical factors defined in the Technical Specifications, Technical Requirements Manual, COLR and Fuel Warranty must be maintained within the limits specified.
-6. Confirm that the following Level 1 Acceptance Criterion is satisfied: The activity of gaseous and liquid effluents must conform to current plant governing documents limitations.
_7.
Confirm that the following Level 2 Acceptance Criterion is satisfied: Water quality is known at all times and remains within the requirements of the SSES Chemistry program.
Confirmed By Date Page 1 of 1
IFor Information Only 09 Attachment T TP-1 99-013 Revision 0 Page 65 of 70 ST-10 IRM PERFORMANCE Mode 4 or Mode 5 Testing: Completion of the following steps satisfies ST 10 requirements that must be met prior to entering Mode 2.
- 1.
Confirm that 184DAY IRM CALIB CHANNEL A S1-178-301A is current (NIMS Activity #Z0852-01) 1158873.
__ 2.
Confirm that 184DAY IRM CALIB CHANNEL B SI-178-301B is current (NIMS Activity #Z0851-01) 1159234.
- 3.
Confirm that 184DAY IRM CALIB CHANNEL C SI-1 78-301C is current (NIMS Activity #Z0850-01) 1159233.
__ 4.
Confirm that 184DAY IRM CALIB CHANNEL D SI-1 78-301D is current (NIMS Activity #Z0849-01) 1159591.
- 5.
Confirm that 184DAY IRM CALIB CHANNEL E SI-1 78-301 E is current (NIMS Activity #Z0848-01) 1159231.
- 6.
Confirm that 184DAY IRM CALIB CHANNEL F SI-1 78-301F is current (NIMS Activity #Z0847-01) 1159592.
- 7.
Confirm that 184DAY IRM CALIB CHANNEL G SI-1 78-301G is current (NIMS Activity #Z0846-01) 1159232.
__ 8.
Confirm that 184DAY IRM CALIB CHANNEL H SI-1 78-301H is current (NIMS Activity #Z0845-01) 1159593 Confirrmed By Date Page 1 of I
For Information Only Attachment U TP-199-013 Revision 0 Page 66 of 70 ST-2 RADIATION MEASUREMENTS Enter Test Condition Completion of the following steps satisfies the requirements for ST 2.
- 1. Confirm completion of HP-TP-521.
- 2. Confirm that the following Level 1 Acceptance Criterion is satisfied: The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of The Standard for Protection Against Radiation as outlined in 10CFR20.
- 3. Confirm that the following Level 2 Acceptance Criterion is satisfied: The radiation*
doses of plant origin shall meet the following limits depending upon the Radiation Zone in which the radiation measurement point is located:
FSAR Radiation Zone Limit (FSAR Table 12.3-1)
< 0.5 mRem/hr II
_< 2.5 mRem/hr III
- 15 mRem/hr IV
< 100 mRem/hr Note: All areas designated Radiation Zone V have potential radiation doses of 100 mRem/hr. Readings taken in Zone V during the EPU Test Program may be less than 100 mRem/hr; however, since Zone V is defined in terms of potential levels, there are no Acceptance Criteria for Zone V survey points.
Confirmed By Date Page 1 of 1
or Information Only Attachment V TP-199-013 Revision 0 Page 67 of 70 ST-22 PRESSURE REGULATOR Enter Test Condition and complete the corresponding section. Use a separate copy of this attachment for each Test Condition. Perform the following steps:
In Test Condition A
- 1.
Record power level at which the TURB CV FAST CLOSURE & STOP VLV TRIP BYPASS Alarm (AR-103 window E03) cleared, AND Confirm that it cleared before exceeding 26% power. This step N/A for all other conditions.
Power Level
/
Confirmed By Date In Test Condition A or at 60% power, prior to first Pressure Regulator Step Change test. N/A this section for all other conditions
- 2.
Confirm Incremental Regulation data and Control Valve position data was collected as required.
- 3.
Confirm actual Control Valve position is within +1% to -3% of predicted values as required by Level 2 Acceptance Criterion.
Confirmed By Date In Test Condition A at 60% power, Perform remaining steps. N/A this section for all other conditions.
__ 4.
Confirm all observed decay ratios were less than 1.0 as required by Level 1 Acceptance Criterion.
__ 5.
Confirm all observed decay ratios were less or equal to 0.5 as required by Level 2 Acceptance Criterion.
__ 6.
Confirm all pressure response times were less than or equal to 10 seconds as required by Level 2 Acceptance Criterion.
__ 7.
Confirm all steam flow steady state limit cycles produced steam flow variations no larger than +/-0.5% as required by Level 2 Acceptance Criterion.
B. Confirm peak neutron flux remained below scram setting by at least 7.5% as required by Level 2 Acceptance Criterion.
Page 1 of 3
4 Sor Information Only Attachment V TP-1 99-013 Revision 0 Page 68 of 70
__9.
Confirm peak vessel pressure remained below scram setting by at least 10 psi as required by Level 2 Acceptance Criterion.
Confirmed By Date In test Conditions 8 through D, Perform the following steps. N/A this section for Test Condition A at 60% power and Test Condition E.
1_
- 1.
Confirm Incremental Regulation data, Control Valve position data, and Main Steam Line harmonic data was collected as required.
__2.
Confirm actual Control Valve position is within +1% to -3% of predicted values as required by Level 2 Acceptance Criterion.
__3.
Confirm all observed decay ratios were less than 1.0 as required by Level 1 Acceptance Criterion.
__4.
Confirm all observed decay ratios were less or equal to 0.5 as required by Level 2 Acceptance Criterion.
__5.
Confirm all pressure response times were less than or equal to 10 seconds as required by Level 2 Acceptance Criterion.
__6.
Confirm all steam flow steady state limit cycles produced steam flow variations no larger than +/-0.5% as required by Level 2 Acceptance Criterion.
__7.
Confirm peak neutron flux remained below scram setting by at least 7.5% as required by Level 2 Acceptance Criterion.
__8.
Confirm peak vessel pressure remained below scram setting by at least 10 psi as required by Level 2 Acceptance Criterion.
Confirmed By Date In Test Condition E, Perform the following steps. N/A this section for Test Conditions A through D.
__1.
Confirm Incremental Regulation data, Control Valve position data, and Main Steam Line harmonic data was collected as required.
Page 2 of 3
For Information Only Attachment V TP-1 99-013 Revision 0 Page 69 of 70
- 2.
Confirm the variation in incremental regulation (ratio of the maximum to the minimum value of the quantity, "incremental change in pressure control signal/incremental change in steam flow," for each flow range) meets the following Level 2 Acceptance Criteria:
% of Valves Wide Open Steam Flow Variation 0 to 85%
4:1 85% to 97%
2:1 85% to 99%
5:1
- 3.
Confirm actual Control Valve position is within +1% to -3% of predicted values as required by Level 2 Acceptance Criterion.
- 4.
Confirm that the 3 rd harmonic steam line frequency does not exist with significant amplitude that would require tuning of the second SLRC card.
Confirmed By Date Page 3 of 3
For Information Only Attachment W TP-199-013 Revision 0 Page 70 of 70 ST-24 TURBINE VALVE SURVEILLANCE Enter Test Condition and complete the following. Use a separate copy of this attachment for each Test Condition.
Completion of the following steps satisfies the requirements for ST 24.
- 1.
Confirm reactor did not SCRAM because of the test as required by Level 2 Acceptance Criterion.
- 2. Confirm peak neutron flux remained below scram trip setting by at least 7.5% as required by Level 2 Acceptance Criterion.
- 3. Confirm peak vessel pressure remained below scram setting by at least 10 psi as required by Level 2 Acceptance Criterion.
_4.
Confirm peak heat flux remained below scram trip setting by at least 5.0% as required by Level 2 Acceptance Criterion.
- 5. Confirm reactor did not isolate because of the test as required by Level 2 Acceptance Criterion.
-6.
Confirm peak steam flow in each line remained below the high flow isolation setting by at least 10% as required by Level 2 Acceptance Criterion.
- 7. Confirm peak vessel pressure remained above the steam line low pressure isolation setting by at least 25 psi as required by Level 2 Acceptance Criterion.
Confirmed By Date Page 1 of 1