Text

Submittal of Startup Test Procedures
	ML091530344
Person / Time
Site:	Susquehanna
Issue date:	05/14/2009
From:	Spence W; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PLA-6506
	Download: ML091530344 (112)
	v • d • e

William H. Spence PPL Susquehanna, LLC President and Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel.610.774.3683 Fax 610.774.5019 whspence@pplweb.com MAY 14-2 PP tic, TM U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 OPERATING LICENSE NO. NPF-22 LICENSE CONDITIONS 2.C.(20)(b)8 and 2.C.(20)(c)

PLA-6506 Docket No. 50-388

References:

1) PLA- 6481, Mr. W. H. Spence (PPL) to Document ControlDesk (USNRC),

"SusquehannaSteam Electric Station Unit I OperatingLicense No. NPF-14 License Conditions2.C.(37)(a) and Unit 2 OperatingLicense No. NPF-22 License Conditions2. C.(21)(a) and 2.C.(21)(b)," datedApril 13, 2008.

2) PLA-6510, Mr. W. H. Spence (PPL) to Document Control Desk (USNRC),

"SusquehannaSteam Electric Station Unit I OperatingLicense No. NPF-14 License Condition 2.C.(36)(b)8 and Unit 2 OperatingLicense No. NPF-22 License Condition 2. C.(20)(b)8," dated May 12, 2009.

The purpose of this letter is to submit the information required by the subject License Conditions to the Nuclear Regulatory Commission (NRC).

License Condition 2.C.(20)(b)8 requires:

"PPL shall submit flow-induced vibration related portions of the CPPU startup test procedure to the NRC, including methodology for updating the limit curve, prior to initial power ascension above 3489 MWt."

License Condition 2.C.(20)(c) requires:

"PPL shall prepare the CPPU startup test procedure to include the following:

(1) main steam line strain gauge limit curves to be used up to 114 % of CLTP; (2) specific hold points and their duration during CPPU power ascension; (3) activities to be accomplished during hold points; (4) plant parameters to be monitored; Am(

ksrck,

Document Control Desk PLA-6506 (5) inspections and walk-downs to be conducted for steam, feedwater, and condensate systems and components during the hold points; (6) methods to be used to trend plant parameters; (7) acceptance criteria for monitoring and trending plant parameters and conducting the walk-downs and inspections; (8) actions to be taken if acceptance criteria are not satisfied; and (9) verification of the completion of commitments and planned actions specified in its application and all supplements to the application in support of the CPPU license amendment request pertaining to the steam dryer prior to power increase above 3489 MWt. PPL shall provide the related CPPU startup test procedure sections to the NRC by facsimile or electronic transmission to the NRC project manager prior to increasing power above 3489 MWT."

The Attachment provides the following three procedures, which collectively include the topics required by License Conditions 2.C.(20)(b)8 (except for the limit curve update methodology which was provided by Reference 2) and 2.C.(20)(c):

" TP-299-010 - "Extended Power Uprate Master Test Procedure (SICT/E)"

" TP-262-033 - "Steam Dryer and Flow Induced Vibration Testing"

" OI-TA-008 - "Shift Technical Advisor Responsibilities" Attachment H.

PPL plans to increase Unit 2 power up to 3733 MWt (107% of CLTP) as previously described in Reference 1. The procedures will be submitted again for future power increases above 3733 MWt to fulfill the requirements of LC 2.C.(20)(c).

If you have any questions or require additional information, please contact Mr. Duane L. Filchner at (610) 774-7819.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: '.5,--/V-&I C/

W. H. Spence

Attachment:

Startup Test Procedures

Document Control Desk PLA-6506 Copy: NRC Region I Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager

Attachment to PLA-6506 Startup Test Procedures

For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE EXTENDED POWER UPRATE MASTER TEST PROCEDURE TP-299"010 SPECIAL, INFREQUENT OR COMPLEX TEST/EVOLUTION Revisionl 0 (SICT/E) Page 1 of 61 ADHERENCE LEVEL: STEP-BY-STEP QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

( ) Non-QA Program ( ) Non-pIant (X) QA Program j

(X)

( )

Plant Instruction EFFECTIVE DATE: 9 0 PERIODIC REVIEW FREQUENCY: N/A PERIODIC REVIEW DUE DATE: N/A RECOMMENDED REVIEWS:

Operations, Reactor Engineering, EPU Engineering, Station Engineering Procedure Owner: Robert G. Sheranko Responsible Supervisor: Dale F. Roth Responsible FUM: Manager-Station Engineering Responsible Approver: Vice President-Nuclear Operations FORM NDAP-QA-0002-1, Rev. 4, Page 1 of 1 (Electronic Form)

For Information Only TP-299-01 0 Revision 0, Page 2 of 61 PROCEDURE REVISION

SUMMARY

TITLE: EXTENDED POWER UPRATE MASTER TEST PROCEDURE SPECIAL, INFREQUENT OR COMPLEX TEST/EVOLUTION (SICT/E)

1) New issue - developed using TP-1 99-009 as a guide.

For Information Only TP-299-01 0 Revision 0 Page 3 of 61 TABLE OF CONTENTS SECTION PAGE

1. PURPOSE/SCOPE 6

2. DISCUSSION 6

3. REFERENCES 8 4, TEST EQUIPMENT 9

5. PRECAUTIONS/NOTES 10

6. PREREQUISITES 11

7. PROCEDURE 11 7.1 Mode 5 / Mode 4 Testing 11 7.2 Preparations for entering Mode 2 12 7.3 Startup to 77% Power 14 7.4 Test Condition B Testing 17 7.5 Test Condition C Testing 18 7.6. Preparation for Power Ascension Above 3489 MWt (88.2%) 20 7.7 (Start of SICT/E Section) Initial power ascension above 3489 MWt. 22 7.8 Test Condition D Testing 25 7.9 Preparation for Power Ascension Above 3611 MWt (91.3%) 27 7.10 (Start of SICT/E Section) Initial power ascension above 3611 MWt (91.3%). 28 7.11 Test Condition E Testing 31

8. RESTORATION 34

9. ACCEPTANCE CRITERIA 34

10. REVIEW 34

11. RECORDS 35

For Information Only TP-299-01 0 Revision 0 Page 4 of 61 TABLE OF CONTENTS (cont'dA ATTACHMENTS ATTACHMENT PAGE A Test Control Documentation 36 B EPU Test 42 - Required i&C Surveillances 37 C Test Condition A Review Summary 38 D EPU Test Condition Definitions 39 E Test Condition B Review Summary 40 F Test Condition C Review Summary 41 G ST-i B Moisture Carryover Testing 42 H Unit 2 Station Verification of Activities for Power Ascension 43 Test Condition D Review Summary 44 J EPU Test Program Power Ramp Data 45 K Test Condition E Review Summary 46 L ST-12B RBM Testing 48 M ST-12A APRM Testing 49 N ST-19 Core Performance Testing 50 0 Test Plateau Review Record 51 P Deleted - Not used during U2-14RIO Startup 52 Q Final Test Program Review Record 53 R TP-299-010 Subtest Numbers 54 S ST-1 A Chemical and Radiochemical 56

For Information Only TP-299-010 Revision 0 Page 5 of 61 ATTACHMENTS ATTACHMENT PAGE T ST-10 IRM Performance 57 U ST-2 Radiation Measurements 58 V ST-22 Pressure Regulator. 59 w ST-24 Turbine Valve Surveillance 61

L For Information Only TP-299-01 0 Revision 0 Page 6 of 61 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 2 Phase 1 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.

1.3 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 2 Phase 1 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 2 Phase I EPU Test Program are as follows:

2.4.1 TC A - Reactor power less than 3489 MWt (88.2%) 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.)

2.4.2 TC B - Reactor power between 3077 and 3140 MWt (77.9% and 79.4%) with any core flow within the safe operating region of the Power/Flow Map.

2.4.3 TC C - Reactor power between 3419 and 3489 MWt (86.5% and 88.2%) with any core flow within the safe operating region of the Power/Flow Map.

For Information Only TP-299-010 Revision 0.

Page 7 of 61 2.4.4 TC D - Reactor power between 3539 and 3611 MWt (89.5% and 91.3%) with any core flow within the safe operating region of the Power/Flow Map.

2.4.5 TC E - 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.

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 2 Phase 1 EPU Test Program are as follows:

2.5.1 88.2% Power Test Plateau - Includes startup and operation up to and including 88.2% power which includes TC A, TC B, and TC C.

2.5.2 91.3% Power Test Plateau - Includes startup and operation up to and including 91.3% power which includes TC D.

2.5.3 94.4% Power Test Plateau - Includes startup and operation up to and including 94.4% 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. Th6 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. xis 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 pa'rtial implementations of the test xy when the test as specified in the test specification is not fully implemented in a Test Conidition, 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 1bther. To clarify pipe vibration testing, Test 100 contains all testing required in M-1563 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, pr6vide 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-299-01 0 Revision 0 Page 8 of 61 2.9 Those sections of this procedure that provide direction to initially increase power beyond 3489 MWt are classified as SICT/Es as these sections represeInt 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 GO-200-002, Plant Startup, Heatup, and Power Operation 3.2 NDAP-QA-0320 "Special, Infrequent or Complex Test/Evolutions" 3.3 NDAP-QA-0008 'Procedure Writers Guide" 3.4 CH-SY-026 Moisture Carryover 3.5 TP-245-029 Feedwater Master Water Level Controller MWLC Tuneupi(SICT/E) 3.6 TP-264-032, Core Flow Calibration 3.7 SR-278-012, LPRM Calibration Validation 3.8 M-1 563, Nuclear Engineering Specification for Extended Power Uprate Startup Testing 3.9 NDAP-QA-0406, Extended Power Uprate Test Program 3.10 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.

3.11 PLA-6242, "Susquehanna Steam Electric Station Proposed License Amendment No. 285 for Unit 1 Operating License No. NPF-1 4 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."

3.12 TP-055-001 "CRD Stroke Time and Friction Measurement" 3.13 TP-293-041 "EPU EHC Pressure Regulator Testing" 3.14 SO-200-007 "Daily Surveillance Operating Log" 3.15 NDAP-QA-0450 "Extended Power Uprate Project Implementation" 3.16 RE-081-036 "Core Fuel Pool Verification"

For Information Only TP-299-0110 Revision 0 Page 9 of 61 3.17 RE-OTP-201 "TIP Uncertainty" 3.18 SC-233-1 01 "U2 TB Vent Weekly Iodine & Particulate Activity" 3.19 SC-233-102 "U2 TB Vent Monthly Tritium & Grab Sample Analysis" 3.20 SC-243-101 "U2 Main Condenser Air Ejector Monthly Noble Gas" 3.21 SC-276-101 "U2 Rx Coolant Conductivity Determination" 3.22 SC-276-102 "U2 Primary Coolant Specific Activity Dose Equivalent i-131" 3.23 SC-276-106 "U2 Rx Coolant Chloride and pH Determination" 3.24 SE-278-001 "APRM 1 Drive Flow Calibration" 3.25 SE-278-002 "APRM 2 Drive Flow Calibration" 3.26 SE-278-003 "APRM 3 Drive Flow Calibration" 3.27 SE-278-004 "APRM 4 Drive Flow Calibration" 3.28 SI-264-305 "Recirc MG Set Positioners High Speed Stops" 3.29 SR-200-008 "In Sequence Critical and Shutdown Margin Demo."

3.30 SR-255-004 "Scram Time Measurements of Control Rods" 3.31 TP-200-013 "EPU Data Collection and Extrapolation" 3.32 TP-244-042 "Condensate Pump Trip" 3.33 TP-262-033 "Steam Dryer Vibration Testing" 3.34 TP-299-011 "EPU Temperature Data Collection for Service Water 3.35 SSES Unit 2 Operating License NPF-22 Amendment 253 3.36 AR CR 1075938 3.37 01-TA-008 "Shift Technical Advisor Responsibilities"

4. TEST EQUIPMENT No specific M&TE equipment is necessary to perform this procedure.

For Information Only TP-299-01 0 Revision 0 Page 10 of 61

5. PRECAUTIONS/NOTES 5.1 Sections and steps within sections must be completed in the order listedd 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 2 Operating License Condition 2.C. (20) (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 3489 MWt,. each test plateau increment shall be approximately 3.5% of 3489 '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 2 Operating License Condition 2.C (20) (a) 4, "if any frequency peak from the MSL strain gauge data exceeds the Level 1 limit curve for dryer strains above 3489 MWt, PPL shall return the facility to a power level at which the acceptance criterion is not exceeded. PPL shall resolve the discreparcy, 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."

5.5 Per Unit 2 Operating License Condition 2.C (21) (a), PPL will demonstrate through performance of transient testing on each SSES unit that the loss of one condensate pump will not result in a complete loss of reactor feedwater. The test shall be performed on each unit's CPPU (Constant Pressure Power Uprate) power ascension test program within 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months of achieving and prior to exceeding a nominal power level of 3733 MWt with feedwater and coridensate flow rates stabilized. PPL shall confirm that the plant response to the transient is as expected in accordance with the acceptance criteria that are established. If a loss of all reactor feedwater occurs as a result of the test, the test faildre shall be addressed in accordance with corrective action program requirements and the provisions of the power ascension test program prior to continued operation of the SSES unit above 3489 MWt.

For Information Only TP-299-0 10 Revision 0 Page 11 of'61 5.6 Per Unit 2 Operating License Condition 2.C.(20) (a) 3, PPL shall hold t~ie facility at each 3.5% ascension step to collect data from License Condition 2.C.(20)(a) and 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 6ntil 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after the NRC project manager confirms receipt of transmission.

6. PREREQUISITES 6.1 Complete AND Attach SICT/E Analysis Form for this TP.

Attached By Date

7. PROCEDURE NOTE (1): Sections and steps within sections must be completed in the brder listed unless otherwise specified.

NOTE (2): Tests identified in an Attachment may be completed in any or~der unless otherwise specified.

7.1 Mode 5 / Mode 4 Testing 7.1.1 Perform following steps concerning this Administrative Hold Condition: Mode 2 may not be entered until this Administrative Hold Condition is lifted by step 7.2.5 in this TP or as otlherwise notified by the Vice President-Nuclear Operations.

o a. Issue ZWO specifying Administrative Hold Condition.

O b. Record ZWO number:

Q c. Inform Shift Supervision of Administrative Hold 'Condition.

o d. Confirm that the Administrative Hold Condition and ZWO number have been added to the Unit 2 Unit Sup ervisor Turnover Sheet.

For Information Only TP-299-01'0 Revision 0 Page 12 of 61 o e. Inform Work Week Management 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 o 7,1.2 Confirm-that Shift Supervision is aware that testing identified in Attachment C for Mode 5 or Mode 4 may commence.

Confirmed By Date Shift Supervision O 7.1.3 Perform tests listed in Attachment C 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. I 7.2.1 Confirm the following:

o a. All testing listed in Attachment C with additionaI 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 Ito 800 psig.

5 b. All EPU Test Results Summaries for completed Startup Tests listed in Attachment C 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 dispositibned.

O] d. There are no open Test Exceptions or Subseq.dent Action items related to Test Exceptions that are required to be completed and closed prior to entering Mode 2, Confirmed By Date EPU Test Program Director

For Information Only TP-299-01 0 Revision 0 Page 13 of'61 o 7.2.2 Confirm that Partial 1 of EC 690276 "Extended Power Uprate Implementation" is closed.

Confirmed By Date o3 7.2.3 Confirm that all items in GO-200-002 Attachment A "Unit 2 Station Verification of Activities for Entering Mode 2" have been signed off.

Confirmed By Date Shift Supervision 7.2.4 Permission is granted to:

o a. Enter Mode 2.

o b. Increase reactor thermal power with plant condltions not to exceed 3489 MWt (88.2%) or 108 Mlbm/Hr core flow, Reactor thermal power may briefly exceed 3489 MWt during minor power transients inherent to approyed test procedures.

o c. Perform all remaining tests listed in Attachment C.

o d. Perform all tests listed in Attachments E and F, VP - Nuclear Operation Date 7.2.5 Perform following steps concerning the Administrative' Hold Condition issued in step 7.1.1 that Mode 2 may not be 'entered:

O a. Inform Shift Supervision that the Administrativ6 Hold Condition has been lifted.

O3 b. Confirm that the ZWO has been closed.

O3 c. Confirm that the Administrative Hold Condition and ZWO number have been removed from the Unit 2 Unit Supervisor Turnover Sheet.

Confirmed By Date Shift Supervision

For Information Only TP-299-01 0 Revision 0 Page 14 of '61 7.3 Startup to 77% Power Q 7.3.1 Enter Mode 2 7.3.2 Perform following steps concerning this Administrative Hold Condition: Reactor power may not exceed 3489 MWt (88.2%) until this Administrative Hold Condition is lifted by step 7.7.2 in this TP or as otherwise notified by the Vice President-Nuclear Operations.

Reactor thermal power may briefly exceed 3489 MWt during minor power transients inherent to approved test procedures.

o a. Issue ZWO specifying Administrative Hold Condition.

o b. Record ZWO number:

O c. Inform Shift Supervision of Administrative Hold Condition.

o d. Confirm that the Administrative Hold Condition &nd ZWO number have been added to the Unit 2 Unit Supervisor Turnover Sheet.

o e. Inform Work Week Management to add the Adrpinistrative Hold Condition and associated ZWO number as,a Log Line to the appropriate activity in the station schedule.

Confirmed By Date O 7.3.3 Confirm that Shift Supervision is aware that all tests listed in Attachment C can be performed in any order at reactor 'power levels not to exceed 3077 MWt (77.9%) or at lower power levels as specified in Attachment C. Reactor thermal power may briefly exceed 3077 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date Shift Supervision o 7.3.4 DURING approach to Initial Criticality, perform ST-4, In Sequence Critical and Shutdown Margin Demonstration.

o3 7.3.5 FOLLOWING breaker closure, Commence collection o6f Pressure Regulator Incremental Regulation and Control Valve dadta per ST-22.1. This data should be collected at intervals not to exceed 3% (of scale) reactor power.

For Information Only TP-299-01 0 Revision 0' Page 15 of 61 NOTE: IF Reactor Power is ever reduced below 16%, AND the Reactor Mode is changed from Mode 1 to Mode 2, THEN ST-1'0.2 IRM/APRM overlap is required to be performed.

7.3.6 Perform ST-22.1 Scram Bypass Setpoint Verification during 11 power ascension.

0 7.3.7 Continue power ascension to 60% power.

7.3.8 Perform Feedwater and Pressure Regulator testing.

03 a. Complete TP-299-01 0 Attachment V Section I to satisfy requirements for ST-22.1 performance up to and including 60% power.

0] 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 13 Regulator Step Changes and Pressure Regulator Failure.

Confirmed By Date Reactor Engineering 0] c. Perform TP-245-029, Feedwater Master Water Level Controller Tuneup.

0] d. Perform ST-22.2, Pressure Regulator Step Changes and Pressure Regulator Failure.

0] 7.3.9 Continue power ascension to 65% power.

INOTE: Steps seune 7.3".10 and 7.3.11 may be performed in paral lei or in anyI 01 7.3.10 Perform the following in any order or combination:

a. Record a dataset of vibrations as required to b-e taken with Local Vibration Monitoring Instrumentation in accordance 0] with TP-262-033

b. Perform Walkdown of accessible areas in accordance with TP-262-033

For Information Only TP-299-01 0 Revision 0 Page 16 of '61 o c. Perform Remote Walkdown of inaccessible areas in accordance with TP-262-033 7.3.11 Perform MSL vibration testing.

o a. Maintain reactor power within a tolerance of +/- 12 MWt as displayed on PICSY point NBA01.

o b. Record reactor operating conditions at the time MSL data is recorded.

o c. Record two 3-minute segment datasets of MSL Strain Gauges in accordance with TP-262-033.

o d. 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 e. Record a dataset of MSL and FW accelerometers in accordance with TP-262-033 o f. Record a dataset of Recirculation and RHR Strain Gauges in accordance with TP-262-033 o g. Inform Operations that the tolerance of +/- 12 MWt on reactor power is no longer in effect.

O h. Evaluate dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU

i. Confirm that it is acceptable to proceed to the next vibration testing test point.

Confirmed By Date EPU O 7.3.12 Inform Operations that vibration test results are acceptable and that reactor power level may be increased.

13 7.3.13 Perform remaining tests listed in Attachment C.

For Information Only TP-299-01 0 Revision 0 Page 17 of'61 7.3,14 Confirm the following:

13 a. All testing listed in Attachment C has been successfully completed OR Test Exception Reports have been written.

13 b. All EPU Test Results Summaries for completed Startup Tests listed in Attachment C have been reviewed by the Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written.

13 C. All Test Exception Reports have been dispositiohed.

[ 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 Program Director 7A4 Test Condition B Testing 0 7.4.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition B in Attachment P.

o 7.4.2 Confirm that Shift Supervision is aware that all tests lited in Attachment E can be performed in any order at reactor'power levels in the range of 3077 to 3140 MWt (77.9% to 79.4%) or at lower power levels as specified in Attachment E. Reactor thermal power may briefly exceed 3140 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date Shift Supervision O 7.4.3 Perform tests listed in Attachment E.

7.4.4 Confirm the following:

o3 a. All testing listed rin Attachment E has been successfully completed OR Test Exception Reports have bden written.

o1 b. All EPU Test Results Summaries for completed Startup Tests listed in Attachment E have been reviewed by the Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written,

For Informatlon Only TP-299-01 0 Revision 0' Page 18 of 61 o c. All Test Exception Reports have been dispositio'ned.

o d. There are no open Test Exceptions or Correct Condition action items related to Test Exceptions that are Irequired to be completed and closed prior to entering Test Condition C.

Confirmed By Date EPU Test Program Director 7.5 Test Condition C Testing o 7.5.1 Confirm that Shift Supervision is aware that all tests listed in Attachment F can be performed in any order at reactorlpower levels in the range of 3419 to 3489 MWt (86.5% to 88.2%) or at lower power levels as specified in Attachment F. Reactor thermal power may briefly exceed 3489 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date Shift Supervision o 7.5.2 Inform Shift Supervision that reactor power may be increased to 3293 MWt.

o 7.5.3 Perform the following steps in parallel:

o a. Maintain reactor power between 3284 MWt and 3300 MWt (83.3% +/-0.25%).

o b. Record reactor operating conditions at the time the dryer data is recorded.

O c. Record two 3-minute segment datasets of MSL Strain Gauges in accordance with TP-262-033.

o d. AFTER the datasets are recorded, evaluate the measured data to ensure the instrumentation is operatingIproperly.

Correct and repeat the data recording if necessary.

o e. Record a dataset of MSL and FW accelerometers in accordance with TP-262-033.

o f. Record a dataset of Recirculation and RR Strain Gauges in accordance with TP-262-033.

For Information Only TP-299-010 Revision 0 Page 19 of 61 o 7.5.4 Inform shift Supervision to Establish reactor conditions within those defined as EPU Test Condition C in Attachment D).

o 7.5.5 Inform Shift Supervision to Establish AND Maintain reactor power between 3471 MWt and 3489 MWt.

NOTE: Step 7.5.6 may be performed at any time in parallel with Steps 7.5.7 through 7.5.9 or postponed until after Step 7.5.9.

o 7.5.6 Perform the following in any order or combination:

o a. Record a dataset of vibrations as required to bb taken with Local Vibration Monitoring Instrumentation in accordance with TP-262-033.

O b. Perform Walkdown of accessible areas in accordance with TP-262-033.

O c. Perform Remote Walkdown of inaccessible areas in accordance with TP-262-033.

o d. Record a dataset of MSL and FW accelerometbrs in accordance with TP-262-033.

o3 e. Record a dataset of Recirculation and RR Strain Gauges in accordance with TP-262-033.

o 7.5.7 Perform the following steps in any order or combination:

o a. Record reactor operating conditions at the time the MSL data is recorded.

o b. Record two 3-minute segment datasets of MSL Strain Gauges in accordance with TP-262-033.

o1 c. 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 7.5.8 AFTER completion of Step 7.5.7, Inform Operations that the minimum power level of 3471 MWt is no longer in effe6t.

For Information Only TP-299-01 0 Revision 0 Page 20 of 61 o 7.5.9 Request Reactor Engineering to Determine ifan LPRM Calibration is required during Test Condition C. If yes, then perform ST 11 as listed in Attachment F. If not required, then document justification for not performing ST 11 in a Test Exception Report.

o3 7.5.10 Perform remaining tests listed in Attachment F.

7.5.11 Confirm the following:

ol a. All testing listed in Attachment F has been succe',ssfully completed OR Test Exception Reports have been written.

O3 b. All EPU Test Results Summaries for completed 'Startup Tests listed in Attachment F 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 dispositidned.

Confirmed By Date EPU Test Program Director O1 7.5.12 Prepare a Test Plateau Review Record, Attachment O1 to the extent practical for submittal to the TRC, PORC and VP-Nuclear Operations for review and approval.

7.6 Preparation for Power Ascension Above 3489 MWt (88.2%)

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 3489 MWt (88.2%) up to a maximum of 3611 MWt (91.3%)

are resolved and Responsible Supervisor certifies that 'all required work is completed.

Confirmed By Date Supervisor - Corrective Action and Assessment

For Information Only TP-299-01 0 Revision 0 Page 21 of 61 13 7.6.2 Confirm that Partial 2 of EC 690276 "Extended Power Uprate Implementation" is closed.

Confirmed By Date 7.6.3 Confirm that at least 45 days have elapsed since PPL provided the NRC with the as-built dryer stress reconciliation and load limit curves as required by License Condition 2.C.(20)(b)1.

o a. Date information was provided to NRC.

o b. Line a plus 45 days.

Confirmed By Date o 7.6.4 Confirm that PPL has provided the NRC with the flow-induced vibration related portions of the CPPU startup test procedure including methodology for updating the limit curve as required by License Condition 2.C.(20)(b)8.

Confirmed By Date o 7.6.5 Confirm that PPL has notified the NRC project manager that all appropriate actions required to assure consistency betveen the CPPU containment analysis and SSES Unit I and Unit: 2 operating and emergency procedures have been completed as required by License Condition 2.C.(23).

Confirmed By Date 7.6.6 Confirm the following:

O 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 3489 MWt (88.2%) to a maximum of 3611 MWt (91.3%).

F6r Information-Only TP-299-01 0 Revision 0 Page 22 of 61 0 b. There are no open Test Exceptions or Subsequ6nt Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition 0.

Confirmed By Date EPU Test Program Director O 7.6.7 Complete Attachment H, "Unit 2 Station Verification of 'Activities for power ascension."

O 7.6.8 Confirm that Reactor Engineering is aware that the initial power increase from 3489 MWt to 3611 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 7.6.9 Permission is granted to:

O a. Increase reactor thermal power with plant cond itions not to exceed 3611 MWt (91.3%) or 108 Mlbm/Hr core flow.

Reactor thermal power may briefly exceed 361 i MWt during minor transients inherent to approved test procedures.

o b. Perform all tests listed in Attachment I.

VP - Nuclear Operation Date 7.7 (Start of SICT/E Section) Initial power ascension above 3489 MWt.

NOTE: The initial power ascension above 3489 MWt will be from 3489 MWt (88.2%) to 3611 MWt (91.3%) using recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr.

o 7.7.1 Confirm that SICT/E Briefing is complete AND that F6rm NDAP-QA-0320-2 has been signed by the brief ers AND that Form NDAP-QA-0320-3 has been signed by the attendees.

Confirmed By J Date

For Information Only TP-299-01(0 Revision 0 Page 23 of 61 7.7.2 Perform following steps concerning the Administrative Hold Condition issued in Step 7.3.2 that Reactor power may hot exceed 3489 MWt (88.2%):

0 a. Inform Shift Supervision that the Administrative Hold Condition has been lifted.

O b. Confirm that the ZWO has been closed.

El c. Confirm that the Administrative Hold Condition and ZWO number have been removed from the Unit 2 Unit Supervisor Turnover Sheet.

Confirmed By Date Shift Supervision 7.7.3 Perform following steps concerning this Administrative! Hold Condition: Reactor power may not exceed 3611 MWt ('91.3%) until this Administrative Hold Condition is lifted by Step 7.10.2 in this TP or as otherwise notified by the Vice President-Nucle~ar Operations. Reactor thermal power may briefly exceed 3611 MWt during minor power transients inherent to approved test procedures.

0 a. Issue ZWO specifying Administrative Hold Condition.

o b. Record ZWO number:

o c. Inform Shift Supervision of Administrative Hold Condition.

O d. Confirm that the Administrative Hold Condition and ZWO number have been added to the Unit 2 Unit Supervisor Turnover Sheet.

o e. Inform Work Week Management 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

For Information Only TP-299-01 0 Revision 0 Page 24 of 61

-1 7.7.4 Confirm that Shift Supervision is aware that all tests listed in Attachment I can be performed in any order at reactor power levels in the range of 3539 to 3611 MWt (89.5% to 91.3%) or at lower power levels as specified in Attachment I.

Confirmed By Date Shift Supervision o 7.7.5 Inform TP-262-033 Test Director that we are about to 6ommence the initial power ascension from 3489 MWt (88.2%) to 3611 MWt (91.3%) AND Confirm that all test personnel are prepared to perform assigned duties.

7.7.6 All thermal power ascension ramps above previously ahained thermal power levels must meet the following requirements and be recorded in Attachment J:

a. SICT/E Controls must be established in accordince with NDAP-QA-0320.

b. TP-262-033 and OI-TA-008 test personnel must be in place and ready to monitor and record data.

c. Record the following data at plant conditions prior to starting ramp: reactor MWt and main generator'gross MWe and MVARs.

d. Inform Shiut Supervision or delegated personnel to increase power.

e. Record time at start of power ramp.

f. Record time at end of power ramp.

g. Record the following data at plant conditions following the power ramp: reactor MWt and main generator gross MWe and MVARs.

h. Calculate Ihe earliest time at which the next power ramp may occur in order to maintain a thermal power ascension ramp of less than or equal to 1% / hour.

7.7.7 (End of SICT/E Section)

For Information Only TP-299-010 Revision 0 Page 25 of 61 7.8 Test Condition D Testing 0 7.8.1 Perform testing listed in Attachment I while completing'the remaining steps in this section.

0 7.8.2 Inform Shift Supervision to Maintain reactor power between 3593 MWt and 3611 MWt as displayed on PICSY point NBA01 during vibration testing data collection.

NOTE: Step 7.8.3 may be performed in parallel with Steps 7.8.4 through 7.8.6 or postponed until after Step 7.8.6.

O 7.8.3 Perform the following in any order or combination:

a. Record vibration datasets in accordance with TP-262-033

b. Perform walkdowns in accordance with TP-262-033 o 7.8.4 Perform the following steps in any order or combinatioh:

o a. Record reactor operating conditions at the time the dryer data is recorded.

O b. Record two 3 minute segment datasets of MS!_L Strain Gauges in accordance with TP-262-033.

o c. Evaluate the measured data to ensure the instrumentation is operating properly. Correct and Repeat the data recording if necessary.

O3 7.8.5 AFTER completion of Step 7.8.4, Inform Operations that the minimum power level of 3593 MWt is no longer in effect.

NOTE: IF data analysis shows that dryer strain gauge data exceeds any Level 1 Acceptance Criterion, THEN Reduce reactor power to a level at which the acceptance criterion is not exceeded.

o 7.8.6 Perform a full Limit Evaluation of the recorded dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU

For Information Only TP-299-01 0 Revision 0 Page 26 of, 61 o 7.8.7 Confirm that it is acceptable to proceed to the next vibration testing test point.

Confirmed By Date EPU NOTE: Remaining steps in this section may be completed in iny order.

O 7.8.8 Prepare a steam dryer performance evaluation for 3611 MWt as required by License Condition 2.C.(20)(a)3.

O 7.8.9 Record date and time that information was provided to' the NRC Project Manager.

Date Time Confirmed By Date 7.8.10 Confirm the following:

0 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 Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written.

o c. All Test Exception Reports have been dispositi6ned.

Confirmed By Date EPU Test Program Director o 7.8.11 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and VP-Nuclear Operations for review and approval.

For Information Only TP-299-01 0 Revision 0 Page 27 of 61 7.9 Preparation for Power Ascension Above 3611 MWt (91.3%)

NOTE: Steps 7.9.1 through 7.9.6 may be completed in any order.

Q 7.9.1 Confirm that all CRs and CRAs necessary for power ascension above 3611 MWt (91.3%) are resolved and Responsible Supervisor certifies that all required work is completed.

Confirmed By Date Manager - Corrective Action and Assessment 7.9.2 Confirm that at least 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months have elapsed since the NRC Project Manager confirmed receipt of the steam dryer performance evaluation for 3611 MWt as required by License Condition 2.C.(20)(a)3.

O a. Date and time that NRC Project Manager confirmed receipt of information ÷ o] b. Line b plus 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . _

EO c. Date and time this step is signed off.

Confirmed By 7.9.3 Confirm the following:

o a. There are no open Test Exceptions or Subsequ'ent Action items related to Test Exceptions that are required to be completed and closed prior to increasing power above 3611 MWt (91.3%).

O b. There are no open Test Exceptions or Subsequ~ent 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 Program Director

For Information Only TP-299-010 Revision 0 Page 28 o1 61 0] 7.9.4 Complete Attachment H, "Unit 2 Station Verification of Activities for Power Ascension".

0] 7.9.5 Confirm that Reactor Engineering is aware that the initial power increase from 3611 MWt to 3733 MWt shall be made using recirculation flow along a constant rod line at an average rate not to exceed 1%/ohr.

/

Confirmed By Date Reactor Engineering 7.9.6 Permission is granted to:

0 a. Increase reactor thermal power with plant conditions not to exceed 3733 MWt.

0 b. Perform all tests listed in Attachment K.

/

VP - Nuclear Operation Date 7.10 (Start of SICTIE Section) Initial power ascension above 3611 MWt (91.3%).

NOTE: The initial power ascension above 3611 MWt will be from 3611 MWt (91.3%) to 3733 MWt (94.4%) using recircUlation flow along a constant rod line at an average power ascension rate not to exceed 1%/o/hr.

0- 7.10.1 Confirm that SICT/E Briefing is complete AND that Form NDAP-QA-0320-2 has been signed by the briefers AND that Form NDAP-QA-0320-3 has been signed by the attendees.

/

Confirmed By Date 7.10.2 Perform following steps concerning the Administrative Hold Condition issued in step 7.7.3 that Reactor power may not exceed 3611 MWt (91.3%):

0] a. Inform Shift Supervision that the Administrative Hold Condition has been lifted.

0] b. Confirm that the ZWO has been closed.

For Information Only TP-299-010 Revision 0 Page 29 of 61 Q c. Confirm that the Administrative Hold Condition and ZWO number have been removed from the Unit 2 Unii Supervisor Turnover Sheet.

Confirmed By Date Shift Supervision 7.10.3 Perform following steps concerning this Administrative Hold Condition: Reactor power may not exceed 3733 MWt (94.4%) until this Administrative Hold Condition is lifted by Step 7.11.14 in this TP or as otherwise notified by the Vice President-Nuclear Operations. Reactor thermal power may briefly exceed 3733 MWt during minor power transients inherent to approved test procedures.

o a. Issue ZWO specifying Administrative Hold Condition.

0 b. Record ZWO number:

O c. Inform Shift Supervision of Administrative Hold Condition.

O3 d. Confirm that the Administrative Hold Condition and ZWO number have been added to the Unit 2 Unit Supervisor Turnover Sheet.

O e. Inform Work Week Management 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 o 7,10.4 Confirm that Shift Supervision is aware that a([ tests listed in Attachment K can be performed in any order at reactor power levels in the range of 3658 to 3733 MWt (92.6% to 94.4%) or at lower power levels as specified in Attachment K.

Confirmed By Date Shift Supervision

For Information Only TP-299-01 0 Revision 0 Page 30 of 61 Q 7.10.5 Inform TP-262-033 Test Director that we are about to commence the initial power ascension from 3611 MWt (91.3%) to 3733 MWt (94,4%) AND Confirm that all test personnel are prepatred to perform assigned duties.

7.10.6 All thermal power ascension ramps above previously altained thermal power levels must meet the following requirements and be recorded in Attachment J:

a. SICT/E Controls must be established in accordance with NDAP-QA-0320.

b. TP-262-033 and OI-TA-008 test personnel musi be in place and ready to monitor and record data.

c. Record the following data at plant conditions prior to starting ramp: reactor MWt and main generator gross MWe and MVARs.

d. Inform Shift Supervision or delegated personnel to increase power.

e. Record time at start of power ramp.

f. Record time at end of power ramp.

g. Record the following data at plant conditions following the power ramp: reactor MWt and main generator gross MWe and MVARs.

h. Calculate the earliest time at which the next power ramp may occur in order to maintain a thermal power ascension ramp of less than or equal to 1% / hour.

13 7.110.7 (End of SICT/E Section)

For Information Only TP-299-01 0 Revision 0 Page 31 of 61 7.11 Test Condition E Testing 0 7.11.1 Perform testing listed in Attachment K while completing the remaining steps in this section.

O3 7.11.2 Calculate AND Record date and time by which ST-103 Condensate Pump Trip must be completed by adding 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months (14 days) onto the time and date of initially achieving 3733 MWt as recorded in Attachment J.

DATE TIME 7.11.3 Perform following steps concerning this Administrative, Hold Condition: ST-1 03 Condensate Pump Trip must be conmipleted by the date and time recorded in Step 7.11.2. This Administrative Hold Condition is lifted by Step 7.11.14.

11 a. Issue ZWO specifying Administrative Hold Condition.

o b. Record ZWO number:

o c. Inform Shift Supervision of Administrative Hold Condition.

O d. Confirm that the Administrative Hold Condition' and ZWO number have been added to the Unit 2 Unit Supervisor Turnover Sheet, o e. Inform Work Week Management 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 o 7.11.4 Inform shift Supervision to Maintain reactor power between 3715 MWt and 3733 MWt as displayed on PICSY poin't NBA01 during vibration data collection.

NOTE: Step 7.11.5 may be performed at any time in parallel With Steps 7.11.6 through 7.11.7 or postponed until after Step 7.11.7.

O 7.11.5 Perform the following in any order or combination:

11 a. Record vibration datasets in accordance with TP-262-033

For Information Only TP-299-01 0 Revision 0 Page 32 of 61 o b. Perform walkdowns in accordance with TP-262-033 o 7.11.6 Perform the following steps in any order or combination:

Q a. Record reactor operating conditions at the time-the dryer data is recorded.

o b. Record two 3-minute segment datasets of MSL Strain Gauges in accordance with TP-262-033.

O c. Evaluate the measured data to ensure the instrumentation is operating properly. Correct and Repeat the data recording if necessary.

o3 7.11.7 AFTER completion of Step 7.11.6, Inform Operations (hat the minimum power level of 3715 MWt is no longer in effedt.

NOTE: Steps 7.11.8 through 7.11A10 may be performed in parallel with Steps 7.11.11 through 7.11.16.

o1 7.11.8 Evaluate recorded dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O 7.11.9 Prepare a steam dryer performance evaluation for 3733 MWt as required by License Condition 2.C.(20)(a)3.

O1 7.11.10 Record date and time that information was provided t6 the NRC Project Manager.

Date Time Confirmed By Date 7.11.11 Perform following steps concerning this Administrative Hold Condition: Reactor power may not exceed 3489 MWt (88.2%)

following ST-103 Condensate Pump Trip until this Adr~inistrative Hold Condition is lifted by Step 7.11.14 in this TP or as otherwise notified by the Vice President-Nuclear Operations. The Administrative Hold Condition issued in Step 7.10.3 that reactor power may not exceed 3733 MWt (94.4%) remains in effect.

0] a. Issue ZWO specifying Administrative Hold Condition.

For Information Only TP-299-010 Revision 0 Page 33 of. 61 o b. Record ZWO number:

O c. Inform Shift Supervision of Administrative Hold Condition.

o d. Confirm that the Administrative Hold Condition and ZWO number have been added to the Unit 2 Unit Supervisor Turnover Sheet.

O e. Inform Work Week Management 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 O 7.11.12 Enter date and time that ST-1 03 Condensate Pump Trip was performed. Confirm that test was performed prior to date and time listed in Step 7.11.2.

Date Time Confirmed By Date O 7.11.13 Confirm that ST-103 Condensate Pump Trip test results satisfy Level 1 Acceptance Criteria.

Confirmed By Date 7.11-.14 Perform following steps concerning Administrative Hold Conditions:

0 a. Inform Shit Supervision that the Administrative Hold Condition issued in Step 7.11.11 that reactor power may not exceed 3489 MWt (88.2%) has been lifted.

03 b. Inform Shift Supervision that the Administrative Hold Condition issued in Step 7.11.3 concerning theldeadline for performing ST-1 03 Condensate Pump Trip is lifted.

o c. Inform Shift Supervision that the Administrative Hold Condition issued in Step 7.10.3 that reactor pow'er may not exceed 3733 MWt (94.4%) has been lifted.

[] d. Confirm that the appropriate ZWOs have been closed.

For Information Only TP-299-0 10 Revision 0 Page 34 of 61 o e. Confirm that the appropriate Administrative Hold Conditions and ZWO numbers have been removed from the Unit 2 Unit Supervisor Turnover Sheet.

Confirmed By Date Shift Supervision 7.11.15 Confirm the following:

o a. All testing listed in Attachment K 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 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 dispositic'ned.

O3 7.11.16 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and VP-Nuclear Operations for review and approval.

8. RESTORATION 8.1 Prepare a Final Test Program Review Record, Attachment Q, to the extent practical for submittal to the TRC, PORC and VP-Nuclear Operations for review and approval.

8.2 Verify that the Final Test Program Review has been approved.

Confirmed By Date EPU Test Program 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

For Information Only TP-299-01 0 Revision 0 Page 35 of 61

11. RECORDS 11.1 Transmit completed TP to DCS.

/

Confirmed By Date

For Information Only Attachmer~t A TP-299-01:0 Revision 0 Page 36 of 61 TEST CONTROL DOCUMENTATION Procedure No. TP-299-010 Page of Page 1 of 1

For Information Only Attachment B EPU TEST 42 TP-299-01 0 REQUIRED SURVEILLANCES Revision 0, Page 37 oi 61 Confirm that the following procedures have been successfully completed:

SI-283-304 SI-283-305 SI-283-306 SI-283-307

/

Confirmed By Date Page 1 of 1

0 Attachment C TP-299-01 0 Revision 0 0 Page 38 of 61 0

Test Condition A Review Summary TP-299-010 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 3 Mode 5 RE-081-036 Core Fuel Pool Verification 5.1 Mode 5 or Mode 4 TP-055-O0I CRD Stroke Time 12B Mode 5 or Mode 4 TP-299-010 RBM Calibration Attachment L 42 Mode 5 or Mode 4 TP-299-01 0 I&C Surveillances Attachment B 10.1 Mode 5 or Mode 4 TP-299-010 IRM Surveillances Attachment T 5.2 Mode 4 AND/OR SR-255-004 Scram Time Measurements of Control

< 1580 MWt (40%) Rods, 4 Mode 2 SR-200-008 In Sequence Critical and Shutdown Margin Demo.

22.1 - Every 120 MWI TP-299-010 Pressure Regulator Data Collection (3%) following gen Attachment V sync up to 60% Section I .....

22.2 -2490 MWt (63%) TP-299-010 Pressure Regulator Testing and Data Attachment V Collection Section II 100.SSW -2569 MWt (65%) TP-262-033 Steam Dryer Steady State Vibration Data and Plant Walkdown 11 3039 MWt (76.9%) SR-278-012 LPRM Calibration

+I- 7MWt 12A.2 3039-MWt-(76:9%)* -TPý299-01 0- APRM-Calibration

+1-7MWt After Attachment M LPRM Cal 10.2 When switching GO-200-004 IRWAPRM Overlap from Mode 1 to Mode 2 Page 1 of 1

For Information Only Attachment D TP-299-01 0 Revision 0 Page 39 of 61 EPU Test Condition Definitions 120

Purpose:

NOT FOR CONTROL ROOM USE UNIT 2 FIL_

POWER EPU Test Program Discussion ONLY POWER/FLOW MAP L I APRM Scram Trip Setpoint 110 Initial / Date: RGS / 02/27/09 - -- RGION APRM Rod Block i TABIUTY REGION I 'APM dBokI IIP0 M INOPERABLE IMMEDIATE L I j L Trip Setpoint SCRAM IAW ON-178-002 IF OPRM OPERABLE IMMEDIATE 100 EXIT IAW ON-178-002 92.6-94.;4 %

IMMEDIATELY EXIT IAWON.178-002 a

90 RESTRICTED REGION (As clitlned In Attachment Uto N DAP-GA-0338) --- I-IFABOVEMELLLA BOUNDARY, ,0 4 4 199.5-911.3%

IMMEDIATELY EXIT IAW ON-178-002 80 I I tI I I'.I I I I I I I I 70)

Z.. e - uO I -I- - - r I- I r r r--rr r- T %~ .9-79.4%

4 T-w- Pm- 1 - 1 1- 4r -r-I- ii; f :: ----

o rr- rr -r Ro- Lin e

"* -T--*- _.::, , /

o ie ,j.* , , , , Ao i L ne' 60 0 1-.,4-11*-::1-,,4..:-,-,. -, 1,- ,l~-,4-1 f- TI I I I I I -ii r1 I -I - r I I' FI -I - a-A tL- 1 '- -- Ll I -- -I L 1 L "I -I- A -I- L" L r l rL-fT II t E. 0439 MW J -I-L- ! ! . .... L J .... J. -I-- L-.I. J -I L J - - -

r I 1I 1001 1t>3%ach3.I 50 thermalripoer copl.w/l

.. L~~~~l~~l.-l.~~

_L . I .- _LJ F ' "I- : .- JT

-II_'I --. [TI

L J -TJ .- L- I 40 1 - 11 -oPump -1 -:-- -* 1- -- - r :; '. r I i I U I i U nII ,. i . - -: L i L . r

i I . , L *

I J I I Ap, Lj __ j ,pt L _ .J _ -r ---- -

30 e - 'I T I I I I IPr I Z '

-,-*1Natur l Clculaton-' -*- -r- f- -..

1 1--7 * *- - -- - --- ----- * -r-- -

-1 I AL in IL iIp I.

ll. L I 1-A -_i: IILJ" I II 11._1 ' I i~i*i: * -*i* ,-r -,70 ",- 180 T3-90 ,-*'100 *-,

20 A 30%+/- Speed - L. 1-1+/- W Onema Pump cmpy i 10 0

0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)

NOT FOR CONTROL ROOM USE - FOR INFORMATION ONLY Pace 1 of 1

ftj 0

Attachment E TP-299-01 0 0~

Revision 0 Page 40 of 61 0

Test Condition B Review Summary TP-299-010 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements All Dispositioned 101 TP-200-013 Baseline Data Collection & Extrapolation 12A.2 TP-299-010 APRM Calibration Attachment M 19 TP-299-010 Core Thermal Limits Attachment N 22.2 TP-299-01 0 Pressure Regulator Testing and Data Attachment V Collection Section II 23 TP-245-029 Feedwater Level Setpoint Changes 24 TP-299-010 Turbine Valve Surveillance Attachment W TP-293-041 Page 1 of 1

0 H'

Attachment F TP-299-01 0 0 Revision 0 Page 41 of 61 H-Ct 0

Test Condition C Review Summary TP-299-01 0 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 100.SS 3293 MWt (83.3%) TP-262-033 Steam Dryer Steady State Vibration Data 100.SSW 3489 MWt (88.2%) TP-262-033 Steam Dryer Steady State Vibration Data and Plant Walkdown 101 TP-200-013 Baseline Data Collection & Extrapolation II SR-278-012 LPRM Calibration 12A.2 3489 MWt (88.2%) TP-299-010 APRM Calibration Attachment M 19 TP-299-010 Core Thermal Limits Attachment N IA TP-299-010 Chemical and Radiochemica!

Attachment S 18 TP-299-010 Moisture Carryover Attachment G 2 TP-299-010 Radiation Measurements Attachment U 22.2 TP-299-O10 PressureRegulator Testing and Data Attachment V Collection TP-293-041 23 TP-045-001 Feedwater Level Setpoint Changes 24 TP-299-01 0 Turbine Valve Surveillance Attachment W TP-293-041 32 SO-200O007- Dry-well-Cooling-Attachment A Item 9 Page 1 of 1

For Information Only Attachment G TP-299-01 0 Revision 0 Page 42 oi 61 MOISTURE CARRYOVER SUPPORT DATA ST 1B Moisture Carryover Testing Test Condition Core Flow Completion of the following steps satisfies the requirement of ST 1B:

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 Shift Test Coordinator 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 NFLQ1 NFL02 NFL03 MSL Flow NFF01 NFF02 NFF03 NFF04 Total Feedwater flow FPA1 0 (Mlb/hr) 10 minute average CRD flow (Mlb/hr) NEF52 Reactor Power NBA01 Page 1 of 1

For Information Only Attachment H TP-299-0j 0 Revision 0 Page 43 df 61 Unit 2 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 Page 1 of 1

o1-1 H

Attachment I 0 TP-299-010 H-Revision 0 Page 44 of 61 0 C*

IH 0

Test Condition D Review Summary TP-299-1 0 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 100.PA Initial ascension to TP-262-033 Steam Dryer Vibe Monitoring During 3611 MWt (91.3%) Ascension 100.SSW 3611 MWt (91.3%) TP-262-033 Steam Dryer Steady State Vibration Data and Plant Walkdown 101 TP-200-013 Baseline Data Collection & Extrapolation 12A.2 TP-299-010 APRM Calibration Attachment M 19 TP-299-010 Core Thermal Limits Attachment N 22.2 TP-299-010 Pressure Regulator Testing and Data Attachment V Collection Section 11 23 TP-24S-029 Feedwater Level Setpoint Changes 24 TP-299-010 Turbine Valve Surveillance Attachment W TP-293-041 1B TP-299-010 Moisture Carryover Attachment G Page 1 of 1

0 H1 o

Attachment J TP-299-01 0 Revision 0 Page 45 of61 0 EPU Test Program Power Ramp Data Date SICT/E 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

-Earl iest-'-i me-For-Next-Ramp-Sheet - of Page 1 of 1

0 0

Attachment K TP-299-010 0

Revision 0 Page 46 of 61 Test Condition E Review Summary TP-299-010 Additional Plant Procedure Description Test Completed Results All TERs Summary Subtest Conditions Number Reviewed Dispositioned Number Requirements 100.PA Initial ascension to TP-262-033 Steam Dryer Vibe Monitoring During 3733 MWt (94.4%) Ascension 100.SSW 3733 MWI TP-262-033 Steam Dryer Steady State Vibration (94.4%) Data and Plant Walkdown 100.SS 92 Mlb/hr TP-262-033 Steam Dryer Steady Stable Vibration Core Flow Data 100.SS 108 MIbfhr TP-262-033 Steam Dryer Steady Stable Vibration Core Flow Data 101 Baseline Data Collection & Extrapolation 103 TP-244-042 Condensate Pump Trip 11 SR-278-012 LPRM Calibration 12A.2 3733 MWt TP-299-01 0 APRM Calibration (94.4%) Attachment M 12A.3 SE-278-001 (2)(3)(4) APRM 1 (2)(3)(4) Drive Flow Calibration 19 TP-299-01 0 Core Thermal Limits Attachment N 1A TP-299-010 Chemical and Radiochemical Attachment S 1B 92 Mlb/Hr TP-299-01 0 Moisture Carryover Attachment-G-1B 108 MIb/Hr TP-299-010 Moisture Carryover Attachment G 2 TP-299-01 0 Radiation Measurements Attachment U Page 1 of 2

0 F-h H1 Attachment K TP-299-01 0 I-;-

Revision 0 Page 47 of 61 0 0

Test Condition E Review Summary TP-299-010 Additional Plant Procedure Description Test Completed Results All TERs Summary Subtest Conditions Number Reviewed Dispositioned Number Requirements 22.3 - Every 120 MWI TP-299-010 Pressure Regulator Testing and Data (3%) Attachment V Collection Section )))

32 SO-200-007 Drywell Cooling Attachment A Item 9 35 3733 MWt (94.4%) TP-264-032 Core Flow Calibration 100 MIb/Hr 18 RE-OTP-201 TIP Uncertainty 29.2 SI-264-305 Recirc M-G Sel Positioners High Speed Stops 36 TP-299-011 EPU Temperature Data Collection for Service Water 49 SI-279-360 MSL Rad Monitor Adjustment Page 2 of 2

For Information Only Attachment L TP-299-01 0 Revision 0 Page 48 of 61 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 1 of 1

For Information Only Attachment M TP-299-010 Revision 0, Page 49 of 61 ST 12A APRM TESTING Completion of the following steps satisfies the requirement for ST 12A testing:

1. Perform SO-278-004.

_ 2. Level 1 Acceptance Criterion a, test 12A. Confirm that the APRM system is calibrated consistent with Technical Specifications.

3. Level 1 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 Attachme t N TP-299-010 Revision 0 Page 50 of 61 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-200-007, 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-200-007 item 11.

3. Level 1 Acceptance Criterion b, test 19. Confirm that steady state rea'ctor 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 1 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 Reactot Engineering.

Confirmed By Date Station Engineering Page 1 of 1

For Information Only Attachmerit 0 TP-299-01 0 Revision 0 Page 51 of 61 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 Fýesults 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:

/

EPU Test Program Director Date TRC Meeting:

PORC Meeting:

Test Plateau Review Approved:

I/

VP - Nuclear Operations Date Page 1 of 1

For Information Only Attachmert P TP-299-01 0 Revision 0d Page 52 of 61 Deleted NOTE: This attachment is not used for U2-14RIO but is being left in the TP'to minimize risks associated with deleting an attachment from a procedure with many attachments.

Page 1 of 1

For Information Only Attachment Q TP-299-01!0 Revision 0 Page 53 of 61 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 Resuits 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:

/

VP - Nuclear Operations Date Page 1 of 1

For Information only Attachmer't R TP-299-01 0 Revision 0 Page 54 of 61 TP-299-010 SUBTEST NUMBERS TP-299-010 iniplementing, M-1563 Subtest Descriptionor Procedure Number Number Title Number 1 1A Chemical and Radiochemical TP-299-01 0 Attachment S 1 11B Moisture Carryover TP-299-010 Attachment G 2 2 Radiological Survey Program in Support of the HP-TP-522 Unit 2 EPU Modification 3 3 Core Fuel Pool Verification RE-081-036 4 4 In Sequence Critical and Shutdown Margin Demo. SR-200-008 5 5.1 CRD Stroke Time .tP-055-001 5 5.2 Scram Time Measurements of Control Rods SR-255-004 10 10 IRMWAPRM Overlap GO-200-004 11 11 LPRM Calibration SR-278-012 12 12A.1 Validation of Core Thermal Power Heat Balance RE-2TP-026 12 12A.2 APRM Calibration tP-299-01 0 Attachment P 12 12A.3 APRM 1(2)(3)(4) Drive Flow Calibration SE-278-001 (2)(3)(4)

TP-299-01 0 12 12B RBM Calibration Attachment L 18 18 TIP Uncertainty R E-OTP-201 19 19 Core Thermal Limits TP-299-01 0 Attachment N 22 22.1 Pressure Regulator Incremental Regulation TP-293-041 22 22.2 Scram Bypass Setpoint Verification TP-293-041 Page 1 of 2

For Information Only Attachmerfit R TP-299-01 0 Revision 0 Page 55 oIf 61 TP-299-010 Implementing M-1563 Subtest Descriptionor P,rocedure Number Number Title Number 22 22.3 Pressure Regulator Step Changes and Ctrl Failures TP-293-041 22 22.4 SLRC Eval and Incremental Regulation Evaluation TP-293-041 23 23 Feedwater Master Water Level Controller Tuneup t-P-245-029 24 24 Turbine Valve Surveillance 1P-293-041 29 29.2 Recirc MG Set Positioners High Speed Stops SI-264-305 32 32 Drywell Cooling SO-200-007 Attachment A liem 9 33 NA (Combined into ST 100) 35 35 Core Flow Calibration lfP-264-032 36 36 EPU Temperature Data Collection for Service Water TP-299-011 37 37 Gaseous Radwaste Systems TP-299-01 0 (Combined with ST 1A) Attachment S I&C Surveillances TP-299-01 0 42 42 Attachment B 49 49 MSL Rad Monitor Adjustment SI-279-360 100 100.1 Steam Dryer Steady State Vibration Data tP-262-033 100 100.3 Steam Dryer Vibe Monitoring During Ascension TP-262-033 100 100.4 Plant Walkdown fTP-262-033 101 101 Baseline Data Collection & Extrapolation fP-200-013 103 103 Condensate Pump Trip FP-244-042 Page 2 of 2

For Information Only Attachmert S TP-299-0110 Revision 0 Page 56 of 61 ST-1A CHEMICAL AND RADIOCHEMICAL (Includes ST 37 Gaseous Radwaste)

Enter Test Condition Completion of the following steps satisfies the requirements for ST IA and 37.

1. Confirm that samples have been taken for the following procedures:

a. SC-276-101

b. SC-276-102

c. SC-276-106

d. SC-233-101

e. SC-233-102

f. SC-243-101

2. Inform the EPU Shift Test Coordinator that step 1 has been completed.

___ 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

For Information Only Attachmert T TP-299-0110 Revision 0, Page 57 of 61 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 SI-278-301A is current (NIMS Activity #Z0852-01).

_ 2. Confirm that 184DAY IRM CALIB CHANNEL B SI-278-301B is current (NIMS Activity #Z0851 -01).

3. Confirm that 184DAY. IRM CALIB CHANNEL C SI-278-301C is current (NIMS Activity #Z0850-01).

4. Confirm that 184DAY IRM CALIB CHANNEL D SI-278-301 D is current (NIMS Activity #Z0849-01).

5. Confirm that 184DAY" IRM CALIB CHANNEL E SI-278-301E is current (NIMS Activity #Z0848-01).

6. Confirm that 184DAY IRM CALIB CHANNEL F SI-278-301 F is current (NIMS Activity #Z0847-01).

7. Confirm that 184DAY IRM CALIB CHANNEL G SI-278-301G is current:(NIMS Activity #Z0846-01).

8. Confirm that 184DAY IRM CALIB CHANNEL H SI-278-301H is current (NIMS Activity #Z0845-01)

Confirmed By Date Page 1 of 1

For Information Only Attachment U TP-299-0 10 Revision 0 Page 58 o f 61 ST-2 RADIATION MEASUREMENTS Enter Test Condition Completion of the following steps satisfies the requirements for ST 2.

_ 1. Confirm completion of HP-TP-522.

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 tones 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)

I < 0.5 mRem/hr II. < 2.5 mRem/hr IIl *15 mRem/hr IV < 100 mRem/hr Note: All areas designated Radiation Zone V have potential radiation d6ses of 100 mRem/hr. Readings taken in Zone V during the EPU Test Program mat 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.

Verified By Date Page 1 of 1

For Information Only Attachment V TP-299-0iO0 Revision 0 Page 59 6f 61 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:

SECTION I:

In Test Condition A at 60% power, prior to first Pressure Regulator Step Change test. N/A this section for all other conditions

1. Record power level at which the TURB CV FAST CLOSURE & STOP VAlV TRIP BYPASS Alarm (AR-203 window E03) cleared, and Confirm that it cleared before exceeding 26% power.

Power Level %

Confirmed By Date

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 SECTION II:

In Test Condition A at 63% power, AND In Test Conditions B through D, Perform the following steps. N/A this section for Test Condition A at 60% power and Test Condition E.

S1. 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.

Page 1 of 2

For Information Only Attachment V TP-299-0 0 Revision 0 Page 60 of 61

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 SECTION III:

In Test Condition E, Perform the following steps. N/A this section for Test Conditi6ns A through D.

1. Confirm Incremental Regulation data, Control Valve position data, and Main Steam Line harmonic data was collected as required.

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 2 of 2

For Information Only Attachment W TP-299-01 0 Revision 0 Page 61 of 61 ST-24 TURBINE VALVE SURVEILLANCE Enter 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

For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE STEAM DRYER AND FLOW INDUCED VIBRATION TESTING TP-262-033 Revision 1 Page 1 of 22 ADHERENCE LEVEL: STEP-BY-STEP QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

( ) QA Program (X) Non-QAProgram (X) Plant ( ) Non-Plant

( ) Instruction EFFECTIVE DATE: /Az PERIODIC REVIEW FREQUENCY: N/A PERIODIC REVIEW DUE DATE: N/A RECOMMENDED REVIEWS:

SE, OPs, EPU Design Eng, GE Procedure Owner: Jay Searfoss Responsible Supervisor: SE Supervisor-Mechanical Responsible FUM: Manager-Station Engineering Responsible Approver: Manager-Station Engineering FORM NDAP-QA-0002-1, Rev. 4, Page 1 of 1 (Electronic Form)

For Information Only TP-262-033 Revision 1 Page 2 of 22 TABLE OF CONTENTS SECTION PAGE

1. PURPOSE 4

2. DISCUSSION 4

3. REFERENCES 5

4. TEST EQUIPMENT 5

5. PRECAUTIONS 5

6. PREREQUISITES 6

7. PROCEDURE 7 7.1 MSL Strain Gages (SGs) 7 7.2 MSL Accelerometer Data Acquisition/Analysis (Line B & C) 8 7.3 Feedwater Loop A Accelerometer Data Acquisition/Analysis 8 7.4 Recirculation/RHR Strain Gage Data Acquisition 9 7.5 Recirculation Loop A & B Accelerometer Data Acquisition/Analysis 9 7.6 RHR Valve HV251F015A(B) and HV251F017A(B) Accelerometer Data Acquisition/Analysis 10 7.7 Locally Monitored Acceleration Data Acquisition 10 7.8 Accessible Area Walkdowns 11 7.9 In-Accessible Area Walkdown 12 7.10 Pi Data Sheet Acquisition 12 7.11 OI-TA-008 Data Acquisition 13

8. RESTORATION 13

9. ACCEPTANCE CRITERIA 13

10. REVIEW 15

11. RECORDS 15

For Information Only TP-262-033 Revision 1 Page 3 of 22 ATTACHMENTS ATTACH MENT PAGE A Required Testing 16 B Data Collection/Analysis Support 17 C Guidelines to Evaluate Data Set(s) for Accelerometers 18 Located Inside the Drywell D Guidelines to Evaluate Data Set(s) for Accelerometers 20 Located Outside the Drywell E Guidelines for Evaluation of Data Set(s) for RHR HV251 F01 5A(B) 21

& HV251 F017A(B) Accelerometers F Pi Steam Dryer Data Log Sheet (Info Only) 22

For Information Only TP-262-033 Revision 1 Page 4 of 22

1. PURPOSE This TP collects and analyzes main steam line vibration and other vibration related data to ensure the new steam dryer is able to function within its design parameters at the new Extended Power Uprate (EPU) conditions. In addition, the piping that supplies make-up water to the Rx vessel and systems associated with the piping that carries the steam from the Rx vessel will also be analyzed to ensure EPU is not causing flow induced vibration to exceed the design limits of the piping installations.

The data collected on the Main Steam Lines and Feedwater systems will be compared to pre-established limits. The data collected from the Main Steam Lines (MSL) strain gages will also be compared to analytical limits, which will be used to confirm the Unit 2 non-instrumented steam dryer structural integrity.

2. DISCUSSION Extended Power Uprate (EPU) is increasing the overall output of the Unit 2 Reactor by approximately 7% power. After attaining 3489 MWt power (original 100% power), output will be increased in increments of approximately 3.5% power to the new 94.4% power (3733 MWt). A new Rx vessel steam dryer has been installed to accommodate the increased steam flows and resultant increases in dryer loading. The Unit 2 power ascension program will ensure that the new steam dryer, existing associated water make-up systems to the Rx vessel and associated steam systems will function within their design limits during EPU. Data will be collected at specific power ascension test points and the data will be analyzed to ensure Unit 2 systems and components are functioning within their design parameters. When directed by other procedures, this TP will collect the data specified for the Test Point, and analyze the collected data. Strain gages, accelerometers, installed plant instrumentation and visual inspections will be employed to ensure the Unit 2 Systems and components are operating within their design limits. The level and amount of data collection will vary with each test point. This TP will identify the data that is to be collected at each of the required test points (See Attachment A). Other procedures will be used to set the required plant conditions. This TP only collects and analyzes data and does not manipulate or alter the status of any plant components. TP-299-01 0 will establish plant conditions and direct the implementation of this TP at the specified test conditions. Once a test condition has been established, then this TP will collect and analyze the data required for the specified test point.

Steam Dryer Instrumentation is not installed on the Unit 2 steam dryer. Data collected from the Unit 1 main steam lines strain gages was used as a bench mark to develop/validate the Main Steam Line (MSL) Limit Curves that will be used to confirm the structural integrity of the Unit 2 Rx vessel steam dryer. Unit 2 MSL strain gage data will be collected at specified power levels and used to confirm the steam dryer structural integrity against the MSL Limit Curves.

For Information Only TP-262-033 Revision 1 Page 5 of 22 The Recirculation/RHR strain gages are included for data collection purposes only; since the piping is negligibly affected by EPU, these data reviews and analyses are not part of this procedure.

3. REFERENCES 3.1 EC-PUPC-2070, Rev 0, EPU Flow Induced Vibration Testing and Walkdown Criteria 3.2 EC-PUPC-2097, Rev. 0, Unit 2 Main Steam Line Strain Gauge Limit Curves 3.3 TP-299-01 0, EPU Master Test Procedure Special, Infrequent or Complex Test/Evolution (SIC/TE) 3.4 USNRC Letter, R.V. Guzman (NRC) to B.T. McKinney (PPL), "Susquehanna Steam Electric Station, Units 1 and 2 Issuance of Amendment Regarding the 13-Percent Extended Power Uprate (TAC Nos. MO-3309 and MO-331 0)," dated January 12, 2008.

3.5 EWR 1052304 Unit 2 MSL Strain Gage Replacement 3.6 EC 770967, EPU-Steam Dryer Upgrade-Unit 2 3.7 EC 690276, EPU Phase Implementation 3.8 OI-TA-008, Rev. 12, Shift Technical Advisor Responsibilities

4. TEST EQUIPMENT None

5. PRECAUTIQNS 5.1 Provide notification to personnel involved in data collection and/or data analysis sufficiently ahead of scheduled testing to ensure personnel availability. Refer to Attachment B for a listing of personnel requirements for each type of data collection.

5.2 At each Test Point, a clean copy of this TP will be used to collect data and to direct the analysis/review of this data.

5.3 TP-299-01 0 Test Director and Shift Manager shall be notified immediately if Level 1 Criteria is exceeded; exceeding Level 1 criteria will require the Rx power and/or flow to be lowered to a level where Level 1 Acceptance Criteria is not being exceeded.

For Information Only TP-262-033 Revision 1 Page 6 of 22

6. PREREQUISITES Q 6.1 Identify the test point that data will be taken and which parts of Section 7.0 will be performed (Refer to Attachment A).

Test Point:

Procedure sections to be performed:

Sample sets (# of and duration) Two (2) Sample Sets @ Three (3)

Minute duration Confirmed By o 6.2 Notify those individuals required to support data collection and analysis at the specified Test Point. (Refer Attachment A for data collection types required at the specified Test Point and Attachment B for the personnel required for each type of data collection).

Confirmed By o 6.3 Confirm a briefing has been completed for the performance of this TP.

Confirmed By 6.4 Confirm the following data collection systems are available to collect data in support of this TP:

0 6.4.1 PPL VDAS is functional 0 6.4.2 PPL VXI is functional Confirmed By Q 6.5 Shift Supervision concurs with the start of this TP.

Shift Supervision

For Information Only TP-262-033 Revision 1 Page 7 of 22 jJ 6.6 Test Personnel are on station to perform data collections per those sections of 7.0 specified in Step 6.1.

Confirmed By

7. PROCEDURE NOTE (1): Data Collection types specified for each Test Point shall be worked in parallel.

NOTE (2): Data Collection type shall be repeated to obtain the required number of data sets specified in Step 6.1 and/or to obtain a Data Set adequate for analysis.

7.1 MSL Strain Gages (SGs) 13 7.1.1 Collect MSL SGs data set(s), using the VXI equipment, for specified time frame.

Confirmed By 7.1.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By 03 7.1.3 EPU Engineering to Analyze and Compare data to the criteria defined in EC-PUPC-2097.

Confirmed By 0: 7.1.4 Incorporate the data set(s) into Test Point Report.

Confirmed By

For Information Only TP-262-033 Revision 1 Page 8 of 22 7.2 MSL Accelerometer Data Acquisition/Analysis (Line B & C)

Q 7.2.1 Collect MSL Accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By O 7.2.2 Confirm data set is acceptable for submitting to EPU Engineering for Analysis.

Confirmed By o 7.2.3 EPU Engineering to Analyze and Trend data set(s) against criteria provided in Attachment C.

Confirmed By o 7.2.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.3 Feedwater Loop A Accelerometer Data Acquisition/Analysis o3 7.3.1 Collect FW Loop 'A' Accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By o 7.3.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By o 7.3.3 EPU Engineering to Analyze and Trend data set(s) against criteria provided in Attachment C.

Confirmed By

For Information Only TP-262-033 Revision 1 Page 9 of 22 Q 7.3.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.4 Recirculation/RHR Strain Gage Data Acquisition O 7.4.1 Collect Recirculation/RHR strain gage data set(s), using the VXI equipment, for specified time frame.

Confirmed By o 7.4.2 Confirm data set is acceptable for submitting to EPU Engineering.

Confirmed By 7.5 Recirculation Loop A & B Accelerometer Data Acquisition/Analysis O 7.5.1 Collect Recirculation Loop A & B Accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By o 7.5.2 Confirm data set is acceptable for submitting to EPU Engineering for Analysis.

Confirmed By o 7.5.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment C.

Confirmed By o 7.5.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By

For Information Only TP-262-033 Revision 1 Page 10 of 22 7.6 RHR Valve HV251F015A(B) and HV251F017A(B) Accelerometer Data Acquisition/Analysis o 7.6.1 Collect RHR valves HV251F015A(B) and HV251F017A(B) accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By O 7.6.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By Q3 7.6.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment E.

Confirmed By o 7.6.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.7 Locally Monitored Acceleration Data Acquisition o 7.7.1 Collect locally monitored acceleration data set(s), using the hand held equipment, for specified time frame.

Confirmed By o 7.7.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By

For Information Only TP-262-033 Revision 1 Page 11 of 22 0 7.7.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment D.

Confirmed By E0 7.7.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.8 Accessible Area Walkdowns NOTE: Not all walkdowns identified in Part C, Table 1, of EC-PUPC-2070 must be performed each time.

0] 7.8.1 Perform walkdowns of areas specified in Part C, Table 1, of EC-PUPC-2070.

Confirmed By 01 7.8.2 Evaluate walkdown results against criteria provide in Part C of EC-PUPC-2070.

Confirmed By 01 7.8.3 Confirm the specified area walkdowns are complete and results have been submitted for Test Point Report.

Confirmed By

For Information Only TP-262-033 Revision 1 Page 12 of 22 7.9 In-Accessible Area Walkdown NOTE: Not all walkdowns identified in Part D, Table 1, of EC-PUPC-2070 must be performed each time.

01 7.9.1 Perform walkdown of areas specified in Part D, Table 1, of EC-PUPC-2070 for this Test Point.

Confirmed By 01 7.9.2 Evaluate walkdown results against criteria provide in Part D of EC-PUPC- 2070.

Confirmed By 01 7.9.3 Confirm the specified area walkdowns are complete and results have been submitted for Test Point Report.

Confirmed By 7.10 Pi Data Sheet Acquisition 0] 7.10.1 Determine start and finish times for the data set(s).

Confirmed By 11 7.10.2 Enter the start and finish times into Pi and Obtain print out containing data as specified in Attachment F for each time. (Do Not Fill Out Attachment F)

Confirmed By 0] 7.10.3 Submit the Pi Data Sheet to EPU Engineering for analysis.

Confirmed By

For Information Only TP-262-033 Revision I Page 13 of 22 03 7.10.4 Submit analyzed Pi Data Sheet for incorporation into Test Point Report.

Confirmed By 7.11 O-TA-008 Data Acquisition 0 7.11.1 Collect data set in accordance with Attachment F of O-TA-008 for the time frame(s) specified.

Confirmed By 01 7.11.2 EPU Engineering to review the 01-TA-O08 data for abnormal instrument readings.

Confirmed By

[] 7.11.3 Submit OI-TA-008 data for incorporation into Test Point Report.

Confirmed By

8. RESTORATION None

9. ACCEPTANCE CRITERIA NOTE (1): Acceptance Criteria shall be N/A'd if data collection type is not applicable for the specified Test Point identified in Step 6.1.

NOTE (2): Meeting of Level 2 Acceptance Criteria, by default, causes Level 1 Acceptance Criteria to be met.

0 9.1 MSL SGs data has been analyzed and has been benchmarked against the MSL Limit Curves for this Test Point and data meets the Level 1 and Level 2 Acceptance Criteria specified in EC-PUPC-2097.

Confirmed By EC-PUPC-2097 may be required to be revised to establish MSL Limit Curves based on data collected at the power levels specified in Attachment A.

For Information Only TP-262-033 Revision 1 Page 14 of 22 Q 9.2 MSL B & C accelerations meet the Level 1 and Level 2 Acceptance Criteria specified in Attachment C for this Test Point.

Level 1 Met (Yes/No) Level 2 Met (Yes/No)

Confirmed By Q 9.3 FW Loop A accelerations meet the Level 1 and Level 2 Acceptance Criteria specified in Attachment C for this Test Point.

Level 1 Met (Yes/No) Level 2 Met (Yes/No)

Confirmed By Q 9.4 Recirculation Loop A & B accelerations meet the Level 2 Acceptance Criteria specified in Attachment C for this Test Point.

Level 2 Met (Yes/No)

Confirmed By Q 9.5 RHR Valves HV251 F01 5A(B) and HV251 F01 7A(B) accelerations meet the Screening Criteria specified in Attachment E for this Test Point.

Screening criteria met. (Yes/No)

Confirmed By Q 9.6 Locally monitored acceleration data meet the Level 2 Acceptance Criteria specified in Attachment D for this Test Point.

Level 2 Met (Yes/No)

Confirmed By

For Information Only TP-262-033 Revision 1 Page 15 of 22 U 9.7 Walkdown of Accessible Areas specified in Part C, Table 1.0 of EC-PUPC-2070 are acceptable per the requirements specified in Part C of EC-PUPC-2070 for this Test Point.

Confirmed By Q 9.8 Walkdown of the In-Accessible Areas specified in Part D, Table 1.0 of EC-PUPC-2070 are acceptable per the requirements specified in Part D of EC-PUPC-2070 for this Test Point.

Confirmed By O 9.9 Pi data Sheets have been analyzed and exhibit no signs of abnormal readings for the specified Test Point.

Confirmed By O 9.10 Installed Plant Instrumentation indicates the steam dryer structural integrity is acceptable by review of data collected per Attachment F of OI-TA-008 at the specified Test Point.

Confirmed By

10. REVIEW This TP has been reviewed by the Supervisor-SE-BOP and found to be acceptable.

Confirmed By

11. RECORDS Transmit completed procedure to Document Control Services.

Attachment A TP-262-033 Revision 1 Page 16 of 22 REQUIRED TESTING Types of Data Locally Collection RRVc,s Monitored Test Points F515 D Accels NOTE tite/ Recirc F017 Accessibl Area In-aceCssible Area PiData Collectton MSLSGs MSLAcces FWAccels RHRSGs Accels Accels Walkdown Walkdown Sheet O-TA-008 Note 2

-2569 MWt (65%); Start 3° RiF YES YES YES YES YES YES YES

-3293 MWt (83.3%): YES YES YES YES YES

-3489 MWt (88.2%) YES YES YES YES YES YES YES Initial Power increases between 3489 and 3611 MWt (Hourly YES Note YES YES YES Note YES YES Not YES YES readings) 3 Note 3 Note 3 3 Note 3 3 Note 3 Note 3

-3611 MWt (91.3%) YES YES YES YES YES YES YES Initial Power increases between 3611 and 3733 MWt YES Note YES YES YES Note YES YES Note YES YES (Hourly readings) 3 Note 3 Note 3 3 Note 3 3 Note 3 Note 3 3733 MWt (94.4%) YES YES YES YES YES YES YES 3733 MWt with 92 MIb/Hr Core Row YES YES YES YES YES YES YES 3733 MWt with 108 MIb/Hr Core Flow YES YES YES YES YES YES YES Note 1:Data Collection at each Test Pointcan be added, as deemed necessary, during the Start-up testing. Attachment identifies the minimum required.

Note 2: Enter a YESin this column if visual observation indicates the need formore quantitative analysis of a non-instrumented piping run.

Note 3: Data collection only during the increase in power to 3611and 3733 MWt.Data collected during the increase willbe included in the Test Point Report, along withthe data collected and analyzed at Test Point 3611 and 3733 MWt.

>1 0

0 0

4-t 0

44i 0

H1 Page 1 of 1

0

'-Il H

Attachment B 0 Hn TP-262-033 Fj DATA COLLECTION/ANALYSIS SUPPORT Revision 1 Ol Page 17 of 22 H-Responsible for Data Collection Ready to Collect Responsible for Responsible For Data Responsible for Description Data Data Collected Analyzed/ Reviewed Data Submitted Comments Used to evaluate MSL SGs DAS OPERATORS PPL PM & NSE EPU Engineering EPLI Engineering Steam Dryer MSL, FW EC-PUPC-2070 Accelerometers DAS OPERATORS PPL PM & NSE EPU Engineering EPU Engineering Part A Recirculation Sys EC-PUPC-2070 Accelerometers DAS OPERATORS PPL PM & NSE Design Engineering Design Engineering Part A No Acceptance Recirculation/RHR SGs DAS OPERATORS PPL PM Design Engineering

Design Engineering Criteria RHR Vlvs HV251F015A(B) &

HV251F017A(B) EC-PUPC-2070 Accelerometers DAS OPERATORS PPL PM & NSE Design Engineering

Design Engineering Part E Accessible Area EC-PUPC-2070 Walkdown EPU Engineering EPU Engineering EPU Engineering EPU Engineering Part C In-Accessible Area EC-PUPC-2070 Walkdown EPU Engineering. EPU Engineering EPU Engineering EPU Engineering Part D No Acceptance Pi Data Sheet EPU Engineering EPU Engineering EPU Engineering EPU Engineering Criteria No Acceptance OI-TA-008 On Shift STA On Shift STA On-Shift STA On-Shift STA Criteria Locally Monitored EC-PU PC-2070 Acceleration Data DAS OPERATORS PPL PM & NSE Design Engineering Design Engineering Part B Design Engineering is required if Acceptance Criteria is not met.

Page 1 of 1

For Information Only Attachment C TP-262-033 Revision 1 Page 18 of 22 Guidelines to Evaluate Data Set(s) for Accelerometers Located Inside the Drywell

[NOTE: Steps of Attachment C should be followed sequentially.

A. MSL B, MSL C and FW Loop A

1. Refer to Part A, Table 1,0 of EC-PUPC-2070 for quick reference Level C(D) and Level A(B) Acceptance Criteria for the following Accelerometers:

a. MSL B (Tables 1.0, 2.0 & 2.1) and MSL C (Tables 1.0, 3.0 & 3.1)

Accelerometers

b. FW Loop A (Tables 1.0, 4.0 & 4.1) Accelerometers

2. Evaluate data set(s) against the quick reference Acceptance Criteria of Part A, Table 1.0 of EC-PUPC-2070.

3. If the data set(s) accelerometer values are less than the Level A(B) values specified in Table 1.0, THEN the data set(s) MEET the Level 2 Acceptance Criteria for this Test Point.

4. If the data set(s) contains accelerometer values greater than Level A(B) values specified in Table 1.0, THEN Evaluate the data set(s) values against the Level C(D) values.

5. If the data set(s) accelerometer values are less than the Level C(D) values specified in table 1.0, THEN Evaluate data set(s) against Part A, Table 2.0 (3,0, 4.0) of EC-PUPC-2070 for Level 2 acceptability.

6. If the data set(s) accelerometer values are less than the Level 2 values specified in Table 2.0 (3.0,4.0), ITHE the data set(s) MEET the Level 2 acceptance criteria for this Test Point.

7. If the data set(s) contain accelerometer values greater than the Level 2 values, THEN data set(s) values FAIL Level 2 and MEET Level 1 Acceptance Criteria for this Test Point.

8. If the data set(s) accelerometer values are greater than the level C(D) values specified in Table 1.0, THEN Evaluate data set(s) against Part A, Table 2.1 (3.1, 4.1) of EC-PUPC-2070 for Level 1 acceptability.

9. If the data set(s) accelerometer values are less than the Level 1 values, THEN the data set(s) values FAIL Level 2 and MEET Level 1 Acceptance Criteria for this test point.

Page 1 of 2

For Information Only Attachment C TP-262-033 Revision 1 Page 19 of 22

10. If the data set(s) accelerometer values are greater than the Level 1 values, THEN the data set(s) values FAIL Level 2 and FAIL Level 1 Acceptance Criteria for this Test Point.

B. Recirculation Loop A and B

1. Refer to Part A, Table 1.0 of EC-PUPC-2070 for quick reference B and D Acceptance Criteria.

2. Evaluate data set(s) against the quick reference Acceptance criteria of Part A, Table 1.0 of EC-PUPC-2070.

3. If the data set(s) accelerometer values are less than the Level B values specified in Table 1, THEN the data set(s) meet the Level 2 Acceptance criteria for this Test Point.

4. If the data set(s) accelerometer values are greater than the Level B values specified in Table 1, THEN Evaluate the data set(s) values against the Level D values.

5. If the data set(s) accelerometer values are less than the Level D values specified in Table 1, THEN data set(s) meet the Level 2 Acceptance criteria for this Test Point.

6. If the data set(s) accelerometer values are greater than the Level D values specified in Table 1, THEN data sets values must have a detailed evaluation by Design Engineering.

7. Submit results of Engineering results that show whether data set(s) values meet Level 2 Acceptance Criteria.

Page 2 of 2

For Information Only Attachment D TP-262-033 Revision 1 Page 20 of 22 Guidelines to Evaluate Data Set(s) for Accelerometers Located Outside the Drywell NOTE: Steps of Attachment D should be followed sequentially.

A. Locally Monitored Acceleration Data:

1. Refer to Part B, Table 1.0 of EC-PUPC-2070 for quick reference Level 2 Acceptance Criteria for the General Area Piping Accelerometers.

2. Evaluate data set(s) against the quick reference Acceptance Criteria of Part B, Table 1.0 of EC-PUPC-2070.

3. If the data set(s) accelerometer values are less than the Level 2 values specified in Table 1.0, THEN the data set(s) MEET the Level 2 Acceptance Criteria for this Test Point.

4. If the data set(s) contains accelerometer values greater than Level 2 values specified in Table 1.0, THEN EPU Engineering to Evaluate the data set(s) values and issue AR.

Page 1 of 1

For Information Only Attachment E TP-262-033 Revision 1 Page 21 of 22 Guidelines For Evaluation Of Data Set(s) For RHR HV251FO15A(B) &

HV251 F01 7A(B) Accelerometers

1. Refer to Part E, Table E.1, of EC-PUPC-2070 for Quick Look Screening Criteria for the RHR HV251 F01 5A(B) & HV251 F01 7A(B) valve accelerometers.

2. Evaluate data set(s) against the quick reference Acceptance Criteria of Part E, Table E.1, of EC-PUPC-2070.

3. If the data set(s) exceeds Quick Look Screening Criteria, Contact the Valve Design Engineer to perform a more detailed evaluation of the data set(s).

4. If the data sets are below the Quick Look Screening Criteria values specified in Part E, Table E.1, of EC-PUPC-2070, THEN the Screening Criteria data set(s) MEET the Acceptance Criteria for this Test Point.

Page 1 of 1

For Information Only Attachment F TP-262-033 Revision 1 Page 22 of 22 Pi STEAM DRYER DATA LOG SHEET (Information to be contained in Pi Print-out)

Date/Time Test Point COMPUTER ID VALUE UNITS Thermal Power (Instantaneous) pJ02.nba01 MWth Thermal Power (15 Min Ave.) 02.nbal0l MWth Electrical Power ip02.tra178 MWe Total Core Flow p02.traO26 Mlbm/hr Recirc Loop Flow A p02.traO28 Mlbm/hr Recirc Loop Flow B p02.traO29 Mlbm/hr Core Plate D/P P02.traO27 PSI Steam Flow Line A p02.tral 53 Mlbm/hr Steam Flow Line B P02.tral 54 Mlbm/hr Steam Flow Line C p02.tra155 Mlbm/hr Steam Flow Line D p02.tra156 Mlbm/hr Total Steam Flow p02.traO97 Mlbm/hr Feedwater Flow p02.traO98 Mlbm/hr Feedwater Temperature Line A p02.tra 102 OF Feedwater Temperature Line B p02.tra103 OF Feedwater Temperature Line C pi02.tra104 OF Rx Dome Press Narrow Range p02.tra208 PSIG Rx Dome Press Wide Range p02.tra2O9 PSIG Steam Dome Temperature p02.nfaO5 OF Recirculation Pump A Speed vm.2p401 a/1 a_rrpjac RPM Recirculation Pump B Speed vm.2p401 b/i brrptac RPM Recirculation Pump A Power p02.nrj51 MWe Recirculation Pump B Power p02.nrj52 MWe CRD Cooling Header Flow pI02.nefO3 GPM CRD System Flow p02.nef01 GPM CRD System Temperature p02.ndtO5 OF Bottom head Drain Temperature p02.tra2O6 OF Rx Water Level Narrow Range P02.tral42 Inches H20 Rx Water Level Narrow Range Ig02.nfl02 Inches H20 Rx Water Level Narrow Range p02.nfl03 Inches H20 Rx Water Level Wide Range pJ02.tral 43 Inches H20 Recirc Pmp A vane passing Freq n/a Hz Recirc Pmp B vane passing Freq n/a Hz Recirc Pmp A Motor Freq n/a Hz Recirc Pmp A Motor Freg n/a Hz Page 1 of 1

For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE SHIFT TECHNICAL ADVISOR RESPONSIBILITIES O-TA-008 Revision 12 Page .1 of 25 ADHERENCE LEVEL: INFORMATION USE QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

( ) QA Program (X) Non-QA Program ( ) Plant ( ) Non-Plant (X) Instruction EFFECTIVE DATE: ________

PERIODIC REVIEW FREQUENCY: N/A PERIODIC REVIEW DUE DATE: N/A RECOMMENDED REVIEWS:

Procedure Owner: F Shift Responsible Supervisor: Shift Manager-F Shift Responsible FUM: Manager-Nuclear Operations Responsible Approver: Manager-Nuclear Operations FORM NDAP-QA-0002-1, Rev. 4, Page 1 of 1 (Electronic Form)

For Information Only OI-TA-008 Revision 12 Page 2 of 25 TABLE OF CONTENTS SECTION PAGE

1. PURPOSE 3

2. RESPONSIBILITIES 3

3. REFERENCES 8

4. DEFINITIONS 9

5. INSTRUCTIONS 9

6. RECORDS 13 ATTACHMENTS ATTACHMENT PAGE A STA Assessment Guide 14 B STA Routine 16 C PICSY Display Turn On Codes 17 D STA Action Guidelines 18 E Unit 1 & Common Off Normal Procedures 20 F Unit 2 Off Normal Procedures 21 G Unit 1 RPV Steam Dryer Structural Monitoring 22 H Unit 2 RPV Steam Dryer Structural Monitoring 23 I Unit 1 and Unit 2 RPV Steam Dryer Structural Integrity Monitoring 24

For Information Only O-TA-008 Revision 12 Page 3 of 25

1. PURPOSE The Shift Technical Advisor's (STA's) primary responsibility is to provide Technical Support in accordance with Technical Specification 5.2.2.g to the Shift Manager with regard to the safe operation of the units. When the STA is performing this primary responsibility, all STA routine activities, as described in this 01, become of secondary importance. In addition, this instruction provides a list of responsibilities and guidance for the STA in the performance of duties common to every shift, and specific duties, assigned to various shifts.

2. RESPONSIBILITIES 2.1 Prior to assuming the on-shift STA responsibilities, the on-coming STA is responsible for ensuring that he is sufficiently aware of the plant status to allow his proficient performance in the STA position.

2.2 The off-going STA is responsible for assisting the on-coming STA in becoming aware of the plant status.

2.3 The Shift Technical Advisor's responsibilities include, but are not limited to:

2.3.1 Providing a diagnosis of plant conditions and advising control room personnel on the status of critical plant parameters during major tests, significant plant evolutions, transients and accidents, and advising Shift Supervision on the future course of actions necessary to terminate or mitigate the consequences of the transient or accident. Refer to Attachment D for Guidelines. In the broad spectrum, the STA fulfills this responsibility by continuously and INDEPENDENTLY assessing:

" The reactor core for establishment of shutdown conditions and for adequate cooling.

The plant for continued integrity of the three primary fission product barriers - fuel cladding, reactor coolant pressure boundary, and the primary containment.

The Emergency Plan for timely recognition of those abnormal plant occurrences which satisfy one or more of the Emergency Action Level descriptions.

For Information Only 01-TA-008 Revision 12 Page 4 of 25 Specific actions or activities an STA would be expected to perform during plant transient and/or accident conditions are listed below.

The STA should perform these actions to the fullest extent practicable, giving .consideration to the priorities of the individual situation.

a. Ensure the transient monitoring system is recording the event.

b. Independently Evaluate plant conditions paying particular attention to the reactorfor attainmentand maintenance of adequatecore cooling. Recommend to Shift Supervision adjustments to the chosen crew response where appropriate.

c. Independently Status core shutdown conditions or gauge success of rod drifting efforts during an ATWS by evaluating information available on the Full Core Display, the Rod Drive Control System, neutron monitoring instrumentation and/or by producing one or more OD-7's.

d. Independently Assess the integrity of the primary fission product barriers as evidenced by plant radiological conditions. Communicate any suspected breach to Shift Supervision.

e. Independently Evaluate the E-Plan level and input this assessment to the Shift Manager.

f. Ensure that the Unit Supervisor is aware of Emergency Operating Procedure entry conditions or imminent violations of EOP curves.

g. Independently Assess system and component isolations, initiations and diesel generator starts and Communicate these observations to Shift Supervision.

h. Identify and Inform the Shift Manager of 1, 4, 8 and 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ENS notifications which must be made in response to the event. Prepare these notifications for transmittal to the NRC.

Recognize and Communicate the existence of abnormal trends or anticipated violations of parameter operating bands to Shift Supervision.

For Information Only 01-TA-O08 Revision 12 Page 5.of 25

j. Forecast and Communicate approaches to initiation and isolation setpoints.

k. Forecast and Communicate approaches to Emergency Operating Procedure action levels (ex: 13 psig in the supp chamber and approach of 0 psig while spraying containment).

1. Review expected plant and crew response to approaching initiation and isolation setpoints and EOP action levels with Shift Supervision if the rate of approach permits such dialogue.

m. At the direction of Shift Supervision, Provide parameter status and trends when circumstances prevent the PCO from performing this responsibility. Utilize hard wire instrumentation, if necessary, when SPDS is unavailable.

n. Independently Assess the accuracy of PCO trending on the power to flow map. Communicate any observed discrepancies to the PCO or Shift Supervision.

o. Independently Assess the accuracy of PCO use of the corrected fuel zone table. Communicate any observed discrepancies to the PCO or Shift Supervision.'

p. Independently Monitor critical time limits which require operator action such as the time allowances for re-establishing water above top of active fuel (E-plan) or for closure of a stuck open SRV. Inform the Shift Manager prior to exhausting these limits.

q. Independently Monitor RPV level, RPV pressure, Reactor power and containment parameter information.

Monitor updates of these parameters from the PCO to the US and correct any erroneous communications which might occur.

r. Generate (call-up) the appropriate PICSY format in response to any request for information. Attachment C provides a listing to assist in this activity.

s. At the direction of Shift Supervision, Contact the appropriate outside agency to obtain confirmatory data on meteorological and seismological events.

For Information Only OI-TA-008 Revision 12 Page 6 of 25

t. Act as the contact point for Pa. DEP BRP inquiries and requests for information.

u. Maintain an awareness of the other unit's status.

v. Silence and Evaluate (as applicable) SPING, Seismic Monitor, and SIMPLEX alarms when circumstances prevent the PCO from performing this responsibility.

Report any potentially significant data to Shift Supervision.

No other alarms may be silenced by the STA unless directed by Shift Supervision.

w. Assist the crew by independently referencing OP's, ON's, AR's, EOP Basis, prints or other reference material without compromising other responsibilities. Advise the crew of any pertinent information obtained from these documents.

Attachment E is a summary listing of ON's.

x. Independently Assess the appropriateness of exceeding the 100 0 F/hr cool down limitation. Assist Shift Supervision in developing a plant cool down strategy within the limits designated in the Unit Technical Specifications (<1OO0 F/hr) when appropriate.

y. Utilize the STA Assessment Guide (Attachment A) to assist in the assessment of plant transient and/or accident conditions. The STA Assessment Guide is an aid.

Completion of the STA Assessment Guide is not required.

z. Providing Guidance to the ED-CR in severe accident conditions for cases where the TSC remains unmanned for several hours after the emergency declaration due to severe weather or other extreme circumstance.

2.3.2 Collecting, Analyzing and Evaluating data following a plant transient or scram to identify the cause of the event, Ensuring equipment and systems functioned as designed during the event and during subsequent recovery actions, Determining whether the event was bounded by events described in the FSAR, and Comparing plant response to previous similar events to identify abnormal or degrading trends in system performance. Data collection & retention shall be performed in accordance with 0O-TA-O01, "Event Report Data Collection and Retention". Data Analysis & Evaluation shall be in accordance with OP-AD-327, "Post Reactor Transient/Scram/Shutdown Evaluation."

For Information Only O-TA-008 Revision 12 Page 7 of 25 2.3.3 Providing a technical review and analysis of plant operations from a nuclear safety viewpoint.

2.3.4 Assisting Shift Supervision in the interpretation and application of Technical Specifications and Technical Requirements.

2.3.5 Identifying and Investigating significant anomalies by technical evaluation of observed or monitored conditions.

2.3.6 Performing other engineering duties as assigned.

2.3.7 Assisting Operations Section personnel in researching prints, troubleshooting problems, monitoring equipment, or as otherwise requested.

2.3.8 Performing the items identified in the STA daily/shiftly routine as defined by Supervisor Operations Engineering-SSES. A sample listing of STA routine duties is shown in Attachment B.

2.3.9 Assist and Advise the Operations Shift Supervision involving the reporting of plant conditions as required by 10CFR 50.72, NDAP-QA-0702, NDAP-QA-0703, and NDAP-QA-0720.

2.3.10 Assist and Advise the Operations Shift Staff in the technical investigation/evaluation of operational conditions/evolutions as requested by the Operations Shift Staff, or as deemed appropriate by the STA to enhance plant safety or availability.

2.3.11 Performing Peer Checks when requested.

2.3.12 Providing a review of Reactor Engineering Instructions when a second qualified Reactor Engineer is not available.

2.3.13 Providing oversight to licensed operators in the areas of reactivity changes and core monitoring.

2.3.14 Reviewing Industry Operating Experience and providing information for use in conducting Pre-Job Briefs as requested by Operations Supervision and/or PCO's.

2.3.15 Performing weekly audits of clearance orders (type SC and PP) and preparation of applicability determinations or initiating EWR's for NSE to complete 50.59/72.48 screenings or evaluations as described in Ol-AD-040.

For Information Only OI-TA-008 Revision 12 Page 8 of 25 2.3.16 Monitoring Plant Conditions for changes that have the potential to impact the Risk Calculation (Sentinel/EOOS) Status. When such changes occur, the STA will rerun the Risk Calculation Program, determine the impacts and make the necessary notifications as outlined in this instruction.

2.4 The Assistant Operations Manager-Shift Operations is responsible for assuring that the items of the STA daily/shiftly routine are completed satisfactorily by the STA, and for modifying the routine as necessary.

3. REFERENCES 3.1 NDAP-QA-0702, Action Request and Condition Report Process 3.2 10 CFR 50.72 3.3 NDAP-QA-300, Conduct of Operations 3.4 OP-AD-003, Shift Routine 3.5 NDAP-QA-0703, Operability Determinations 3.6 NDAP-QA-0720, Station Report Matrix and Reportability Evaluation Guidance 3.7 NDAP-QA-0002, Nuclear Department Procedure Program 3.8 NDAP-QA-0338, Reactivity Management and Controls Program 3.9 NDAP-QA-0006, Plant Operations Review Committee 3.10 01-AD-001, Administrative Control of Operations Instructions 3.11 Ol-AD-055, Operations Procedure Program 3.12 Ol-AD-055, Procedure Writer's Guide 3.13 OI-AD-040, System Status File Audits 3.14 Ol-AD-300, Work Control Center WCC Operating Instructions

For Information Only OI-TA-008 Revision 12 Page 9 of 25

4. DEFINITIONS 4.1 STA Assessment Guide (Attachment A) - A check off list of items to assist the STA in the assessment of the plant during transient and/or accident conditions.

The STA Assessment Guide contains reference material such as trip/isolation setpoints and PICSY Displays to allow the STA to access information and assess the plant data in a time efficient manner. The STA Assessment Guide is an aid and is not a permanent record of the event.

5. INSTRUCTIONS 5.1 Each shift shall be preceded by an orderly, efficient turnover of information between the current on-shift STA and the on-coming STA. This turnover shall be of sufficient depth and scope to allow the on-coming STA to perform in a proficient manner. It is strongly recommended that this turnover of information include:

5.1.1 A written summary of the current plant status along with significant operational events which were completed during the previous shift(s), which are on-going, or which are planned for the coming shift. To fulfill this requirement, the following are provided:

STA Turnover Sheet, Form OP-AD-003 update shiftly e Station Status Report - update shiftly 5.1.2 A review of Action Requests (Condition Reports) processed during the past shifts.

5.1.3 A review of 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or shorter term LCO's incurred during the previous shifts.

5.1.4 Significant changes in Control Room indication which have occurred during the past shifts.

5.1.5 A review of any other significant or unusual events or conditions which existed during the previous shifts (i.e., special tests in progress, NRC notifications made via the ENS, Emergency Plan Activities, etc.)

5.1.6 The Offgoing STA will check off each item on the STA Turnover Sheet (Form OP-AD-003-16) when items are completed.

5.1.7 Both the Offgoing and Oncoming STAs will sign the STA Turnover Sheet to document transfer of responsibilities.

For Information Only OI-TA-008 Revision 12 Page 10 of 25 5.2 The STA should Perform the following routine duties:

NOTE: The STA shift routine duties may be altered as appropriate to accommodate non-routine occurrences or conditions.

5.2.1 On each shift, the STA should:

a. Periodically assess plant operation by:

(1) Reviewing the LCO/TRO logs.

(2) Reviewing the Unit logs.

(3) Reviewing SPING data or Rad Effluent Release Data from SPDS as required.

b. Review the STA Log.

c. Ensure the transient monitoring system is in the proper mode of operation to support current plant conditions.

d. Review OPS Surveillance Procedures as appropriate.

e. Review POWERPLEX III operation at the beginning of each shift to ensure:

(1) RDAS backup computer is up (2) Core maximum parameters are less than specified limits. REF: SO-100/200-007.

f. Review the STA's Plant Parameter PI Process Data Book to assist the STA in an understanding of Plant Status and to help identify potential adverse trends.

g. Check SPDS operation and reset isolations as necessary.

h. Review CR's processed by the Unit Supervisors. This review covers both the Unit Supervisor's Operability Determination as well as performance of a Reportability Evaluation in accordance with NDAP-QA-0720.

For Information Only OI-TA-008 Revision 12 Page 11 of 25 As time permits, the STA will periodically Review the Unit Supervisor's CR Inbox in NIMS to determine if there are any CR's with immediate Operability/Reportability concerns and bring them to the attention of Shift Supervision.

j. Monitor Plant Conditions for changes that have the potential to impact the Risk Calculation (Sentinel/EOOS) Status as determined for the week by the Work Week Manager (i.e.,

evaluate for emergent items) as described below:

(1) Monitor AR's/CR's as well as consider any information provided by Shift Supervision or other personnel for equipment related problems.

(2) If there are any potential impacts to the Risk profile for the week, the STA will Recalculate the profile to determine the impacts. Any recalculations that are done are to be logged in the applicable Units Log(s) (to either document the impacts or to document that there were no impacts).

(3) If a change to the Risk Status/profile is identified, the STA will Notify the following personnel to Ensure that work releases are re-evaluated and elements of the Protective Equipment Program are implemented:

Unit Supervisor

Work Control Center

Work Week Manager 5.2.2 In addition to the duties described above, the night shift STA should perform the following duties:

a. Start a new STA Turnover Sheet.

b. Record post midnight data on the STA Plant Status Form and update the Drywell Leakage Log (Excel Spread Sheet).

For Information Only 01-TA-008 Revision 12 Page 12 of 25

c. Provide updates to the Station Status Report issued by Work Management. Additionally, Issue an abbreviated Station Status Report on weekends and holidays when Work Management is not available to issue it. The abbreviated report will contain only the information relevant to Operations (i.e., it will exclude all information following the CR List and information normally provided by other departments, e.g., Health Physics, etc.).

d. Monitor Unit 1 and Unit 2 Steam Dryer Structural Integrity via PI. Attachments G, H, and I contain background information and parameters to be monitored.

5.2.3 In addition, the on-duty STA should Perform the following items as applicable:

a. Individual projects as assigned by the Assistant Operations Manager-Shift Operations.

b. Providing Assistance to various organizations in obtaining transient monitoring and plant computer data.

c. Providing Assistance to Operations in identification of unknown sources of drywell leakage.

d. Advising operators on use of Spray Pond Sprays.

5.3 Routine duties may be changed periodically. Current duties are listed on the "STA ROUTINE LIST," a copy of which is included as Attachment B. This list may be revised as necessary by the appropriate supervision without immediately requiring a corresponding revision to this instruction. (Revision may follow at a later more convenient time.)

5.4 When the operations shift to which an STA is assigned is scheduled for training, the STA shall participate in the assigned training.

5.5 On days when the Screening Team is not scheduled to meet (typically weekends and holidays) the on-duty STA shall review AR's which are in 'Supervisory Review' status and document the last AR Number which was reviewed on the STA Turnover Sheet. If an AR has not been reviewed by the Control Room and is not administrative in nature, the STA shall ensure that it gets the appropriate Control Room Operability/Reportability reviews.

For Information Only OI-TA-008 Revision 12 Page 13 of 25

6. RECORDS Completed STA Turnover Forms should be submitted to the Ops Clerk on a daily basis.

For Information Only Aftachment A OI-TA-008 STA ASSESSMENT GUIDE Revision 12 STA ASSESSMENT GUIDE SHEET 1 Page 14 of 25

']N=I:lAL*:EVENi,".

. .... *-PICSY DISPLAYS.-....

El TRA Initiated TRASTS, TRATRIG E3 Check All Rods In 0D7 o] Verify Isolations, Initiations, and DIG Starts CONTISO

[] SDV Vents and Drains El Main Turbine Speed decreasing TRBB El Check Rx Vessel Level PRIMARY El Check Rx Vessel Pressure PRIMARY, RPRESS E3 SRV Lifts SRV, CONTN El Check Containment Parameters CONTN El Check Rad levels RADEFF El Verify MSL Rads trended down with Power ERADMON El Verify E-Plan Entries (15 Min)

El Evaluate the need for a PAR.

A PAR must be made for General Emergency.

C3 Verify ENS Notification (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

El Rx Power >102% (Unit 1 3807 MWth, Initiate SBLC I Inhibit ADS: NBA01, NBA08 U 2 3807 MWth - NBA01) unit >5% Initial Power- 0D7 More than 1 Control Rod > 00 Immediately, PRIMARY, CORESTAT Initial Reactor Power % <5% Initial Power - PRIMARY, ECCSFL El Rx Power > 5% Before SP Temp =150°F STA

[o Recirc Pumps Tripped 0 Init SBLC/Inhibit ADS E] Power Decreased w/ lowering level El Pressure maintained >800#

El ADS & LP ECCS Inhibited El RPS De-energized?

El Hydraulic Lock?

El CRD Available?, Cross-tie?

El Alt Insertion methods in Progress?

RxVes's.'ýelLevel C Control o k:ii l- _-c-'-

Level Set points reached? Auto Actuation's RWTLVL, ECCSFL, STA El Level 8, +54" + 54 Main Turbine Trip E] Level 3, +13", Auto Act. Complete RRP's Trip El Level 2, -38", Auto Act. Complete + 13 RX SCRAM, RRP (30%)

El Level 1, -129", Auto Act. Complete - 30 RCIC El WR -145", Transition to Fuel Zone - 38 ARI, HPCI, SBGTS, 0l Below TAF, -161" CREOASS, ISO RWCU, FUELZONE Loss - Coolant System Boundary RRP Trip (IOs TD) EOF, STA Potential Loss - Fuel Clad Boundary -129 CS, RHR, D/G, El Below TAF, - 205", Loss Fuel Clad ESW, ADS Timers, Boundary Airborne Release MSIV closure El Fuel Zone < - 290" - Level Indeterminate E2 Adequate Core Cooling? System Design Flow ECCSFL, STA E] Submergence, > -161" Cond/FW 28,800 gpm El Steam Cooling, > -205" (Non-ATWS) HPCI 5000 gpm

[] Systems Injecting R2IC 600 gpm 12 Cond / Feedwater RHR Loop 21,300 gpm H HPCI CS Loop 6,350gpm 40 gpm El RCIC SBLC

[] RHR Loop 'A' CRD 63 gpm El RHR Loop'B' El Core Spray Loop 'A'

[I Core Spray Loop 'B' El SBLC 0l CRD Page 1 of 2

For Information Only Attachment A OI-TA-008 STA ASSESSMENT GUIDE Revision 12 STA ASSESSMENT GUIDE SHEET 2 Page 15 of 25 Rxi~ diiCur'Cbhtr6l -~.~~~~ 7.*

O MSIV's Open ARI - 1135# CONTN, SRV El Bypass Valves & Condenser Available EOC-RPT - SV Closure (5.5%)

O MSIV's Closed CV Fast Closure (500# ETS) PRIMARY, RPRESS El SRV's Cycling SRV Safety Setpoints CONTN El RHR in SPC Condenser Vacuum Trips Pressure Setpoints reached? Main Turb. - 7.5" HgA Nominal USOPSTS

[o 1087# (21.7 HgV) o B61#, MS in Run RFPT 11.8" HgA (17.4" HgV) 0 700# MSL 19.0" HgA (10.2" HgV)

[] Condensate Available BPV's 22.2" HgA (7.0" HgV)

El 420#

0l ECCS Overridden if not Req.

El Containment Isolations Complete? Curves CONTISO El Primary Containment Challenged? PSL- PRESSUPP CONTN El Supp Pool Temps°F (>90 0 F) HCTL- HEATCAP EOF, STA, STEMP El 90*F, RHR in SPC SAT - RPVSAT El 140 0F, Bypass HPCI Swap HEATCAP El 150°F Monitor HCTL El 2301F, use RHR for SP Temps PRESSUPP 12 Supp Pool Level - (<22',>24')

[E 38',RD El 26', Initiate HPCI/RCIC El 22', ECCS Rooms Flooded El <21', Monitor Vortex Limits El <20.5' SPOTMOS lower sensors El 17', Isolate HPCI (Before 17') Vortex Limits STEMP El 12', RD (Before 12' Non ATWS) RHR - 18'

[E DW Press (>1.72#) CS - 15.5' to 21' El Auto Act. Complete El Initiate SC Sprays 1.72 Auto Actuation's PRESSUPP El Supp Chamber Press (>1.72#) - Aux LS, if Gen LO not reset

[] >13#, DW Sprays Initiated - HPCI, D/G, ESW Init.

El H202 Levels (>4%) - RHR, CS Init. if <420#

El DW Temp (>1500F) - RHR, SPC/SPS/DWS Isol El >2120F, monitor SAT curve - HPCI PCM Swap to Inj RPVSAT El 340°F (Before), Spray DW DW Sprays El > 3400F, RD >13# Supp Chamber El Secondary Containment challenged? Before DW Temp = 340°F

[] ARM Alarms EO104, RADRX F- Room Temps RDPAM E] Fire Detection El 749' 4&5 racks- WR -125" to +60" 749' Fire Zones, 4 & 5 racks U I - X218_Z7 U2 - X232_Z5 El Radiation Release in progress Unusual Event (60 min) RADEFF

[] Monitored, (SPINGS Available)? Noble Gas 2.0E+6 p.Ci/min METVENT1 (15 min ave)

E] Unmonitored, Dose Calc's performed? Iodine/Part 3000 mRem/Yr E] Fuel Damage Indicated Alert, E0105 (15 min) CONTN 0l Containment Rads increasing? Noble Gas 2.0E+8 pCi/min ERADMON Cl MSIV Rads increasing? Iodine/Part 3.OE+5 mRem/Yr PROCMON El MSIV Isolation Site EO104, RADRX, RADTB, El ARM Alarms Noble Gas 6.2E+8Ci/min CSRWE, ROPAM, El Blowout Panels Checked, Security General RADMS Noble Gas 6.2E+9pCi/min Page 2 of 2

For Information Only Attachment B 01-TA-008 Revision 12 Page 16 of 25 STA ROUTINE DAY SHIFT Station Status Report Updates (markups)

Clear SPDS Isolations Review Unit Logs Review STA Log Review LCO/TRO Logs Update Turnover Sheet Review the STA's Plant Parameter P1 Process Data Book Review thermal limits Check Backup RDAS availability Check transient monitoring status Review CR's for Operability/Reportability Review AR's in 'Supervisory Review' status (Weekends and Holidays when the Screening Team does not meet)

Perform duties of USW/STA, when assigned NIGHT SHIFT Station Status Report Updates for Work Management (issue reports on weekends and holidays when Work Management is not available)

Clear SPDS Isolations Review Unit Logs Review STA Log Review the STA's Plant Parameter PI Process Data Book Review thermal limits Check Backup RDAS availability Check transient monitoring status Review LCO/TRO Logs Update Turnover Sheet Review CR's for Operability/Reportability Review AR's in 'Supervisory Review' status (Weekends and Holidays when the Screening Team does not meet)

Monitor Unit 1 and Unit 2 Steam Dryer Structural Integrity Perform duties of USW/STA, when assigned Page 1 of 1

For Information Only Attachment C 01-TA-008 Revision 12 PICSY DISPLAY TURN-ON CODES Page 17 of 25 FEDAER HEATER CONDENSATE &.OFFGAS FEEDWATER Feedwater Heaters (In/Out Temps) FWHT Condenser perf/Circ wtr CNDPF Feedwater System FWSYS FW htr str A (Temp-Actual vs. Design) FWSTA Condensate Sys CNDSY RFPT Steam RFPT B FWSTB Cond pump motors CNDPP RFPT Bearing Temps RFPTB C FWSTC Cond Air Removal ARMSY RFPT & RFPT Lube Oil RFPLO FW htr Performance A (Press/Temps) FWAPR RFPT & RFP A RFPA B FWBPR B RFPB C FWCP C RFPC R

Heater Drain Valves HTRDV Vessel level/feeds FWJ Extraction steam valving EXSTV FW Heater Levels (DCS COND/F) CDF

~ N GENERTORW. ý4g~EcTIRJCALDlT .2 Stop/Control Valves TBVLV Main Generator MNGEN 13.8 kv System 13KV HP Turbine HPTB Gen/Altemator cIng GENCL Aux buses AXB12 HP Turb Performance HPPR - DIESELS -,- -' Startup bus 10 SUl Moisture Separators WTRSP D/G A DG-A Startup bus 20 SU20 LP Turbine A LPTBA DIG B DG-B 4160V System 4KV B LPTBB D/G C DG-C Critical motors CRTMO C LPTBC DIG D DG-D Other unit's mtr UNIT I Lube Oil/Brng temps TBLO Lube Oil/EHC LOEHC Vib/Brng metal tamp TBVIB Sealing Steam TBSST

-.CONTAINMENT -" REACTOR - RADMONITORING .

Containment Status CONTN Rx Cooldown A ACDA Rx Bldg RADRX Containment Isolations CONTISO B RCDB Tb Bldg RADTB PSL Curve PRESSUPP Rx Heatup A RHUA CS, RW & Admin RADMS HCTL Curve HEATCAP B RHUB CS & RW CSRWE SAT Curve RPVSAT Shutdown params SHDWN Misc GD E_CSRAD Cont temps/press,SP level CTATM LPRM's LPRM Hi range AR M's RDPAM SP Water templmap,SRV status SRVTEMP SRMAIRM Overlap NMSAE Process Rad GD ERADMON SP water temp/SPOTMOS STEMP IRM/APRM Overlap NMSC EO-104 Table #9 E01 04 SW/RB/TB sumps LRW Reactor Parameters EOF Spings RADEFF DW fans/coolers/RB chillers RBWT Reactor Water LvI RWTLVL Spings (15 Min Avg) METVENT1 Reactor Core Status CORESTAT WATER SYSTEMS . . , . MISC z.:. "--ICS HMI'SCREENS water SPWTR Service water Service SPWTR Unit Performance UPERF A RRP - Runback Reset/ RRPA Circ water CIRWT Chemistry CYCHM Limiter Enable/Disable Circ wtr pp mtr CWPMT CDI/FW cond trend CFW B RRP - Runback Reset/ RRP_B RBCCW RBCCW RWCU/Recirc cond trend RXWC Limiter Enable/Disable TBCCW TBCCW Environmental Cond ENVIR A & B RRP Mode Screens RRP DUAL SCRN ESW EWSTR Emergency Format EOF Combination Feedwater FW OVERVIEW; RHRSW RHR HWC-H2 Flow HYDROGEN Screens FW COMBINED; GRRCCW GRCCW HWC-02 Flow OXYGEN FW SUSD RBCW RBWT CFS CFS A Rx Feed Pump RFP_A CS, TB HVAC CSTB STA Overview STA B Rx Feed Pump RFP_B RWMU MUPWT C Rx Feed Pump RFP_C Cond xfr, Refuel CDRF CPU Monitor CP WD MONITOR Transmitter Status INSTR BYP/RESET Page 1 of 1

For Information Only Attachment D OI-TA-008 Revision 12 Page 18 of 25 STA ACTION GUIDELINES TYPICAL ACTIONS (OVERVIEW)

" Check for immediate operator actions

" Scan for EO entries

" Assess feed and pressure control systems

" Establish trends

" Inform crew of major setpoint approaches (1.72#, -129"...)

" Confirm parameter values

Backup PCO reading Corrected Fuel Zone level

" Backup Emergency Plan calls o Reportability determinations

" Independent plots of Power/Flow TOOLS/TRICKS

" Plot and trend curves on spare EO-103 boards (or use curves on PICSY)

" Keep time line

" Keep "long-term" punchlist (cleanup items; e.g., restore SLC & CRD, restore from ES's, max SPC .... )

" Trend containment parameters by recording parameters periodically

" Watch Supp Chamber pressure, inform US when 13# to continue down SP-P leg of EO-1 03

" Ensure PCO's read Fuel Zone until it "pegs out" when restoring level

Give containment parameters in order of EO-1 03 (SP-T, SP-L, PC-P, SC-P, PC-H, DW-T &

Rads)

Watch Shutdown Range when violating RPV Saturation curve for confirmation

Do not shout out EO-1 03 entries during ATWS, inform US/SS you have entries when he is ready.

Remember SPOTMOS is no good after <20.5 feet, use STEMP Screen & lower RTD's.

PSL probably will not be violated if DW pressure is leading SC pressure; however, SC leads DW, PSL probably will be violated.

Page 1 of 2

For Information Only Attachment D OI-TA-008 Revision 12 Page 19 of 25 EVENT INITIAL EVALUATIONS Ensure TRA tripped Power - All rods in?

- SDV Vent & Drain Valves closed?

- Turbine tripped, speed decreasing, Generator trip?

- ATWS (electrical or hydraulic), RPS Man init, ARI, SLC, Turbine on line, MSIV's open?

SBLC Injection - RWCU isolated?

- Pumps running; injecting and flow?

Pressure Bypass Valves operating, SRV lifts, scrams, EO entry, condenser available?

Level ECCS initiations or anticipated, EO entry?

Containment DW-P/T, SP-T/L, H2 concentrations, EO entries?

Rad Releases Offgas, Refuel Floor, RB, row-of-five, EO entries? MSIVs need to be closed (PICSY E-PLAN MENU formats).

DG starts Voltage, frequency, output breaker/bus voltages?

ESW starts - Ensure DG and ECCS room cooling

- Ensure started manually if HPCI/RCIC auto-start on level ESS power Busses 1 A thru 1D and 2A thru 2D available?

Offsite power Start Up Bus 10 and 20 powered?

Emergency Plan 15 minutes to classify and call, Protective Action Recommendation (PAR) evaluation required. PAR must be made for General Emergency.

Reportability 1,4, 8or24 hour?

Makeup sources MSIV's, RFP's, Condensate, RCIC, HPCI, ORD, SLC, RHR, Core Spray, Condensate Transfer, RHRSW .... ?

Heat Sinks MSIV's Condenser, Circ Water, Bypass Valves, Supp Pool temp Condenser, Circ Water, Service Water, Instrument Air, rad levels, BOP HVAC configuration Isolations SPDS and ON-1 59-002 or ON-259-002 Page 2 of 2

For Information Only Attachment E UNIT 1 AND COMMON OI-TA-008 OFF NORMAL PROCEDURES Revision 12 Page 20 of 25 SCRAM/TRIP: CONDENSER/VACUUM:

" ON-100-101 SCRAM, SCRAM Imminent

ON-070-002 Hi Hi H2 Concentration in Common Offgas RCB

" ON-158-001 Loss of RPS Discharge

ON-193-002 Main Turb Trip

ON-142-001 Circ Water System Leak

" ON-183-001 Stuck Open SRV

ON-143-001 Main Condenser Vacuum & Offgas Sys Off

" ON-184-001 MS Line Isol & Quick Recovery Normal Operation

ON-172-002 Hi Hi H2 Concentration in Unit 1 Offgas RCB REACTIVITY: Discharge

ON-100-004 Rx Power > Authorized Limit CIG/INSTRUMENT AIR:

" ON-1 00-006 Loss of Reactor Heat Balance

ON-1 18-001 Loss of Instrument Air Calculation " ON-125-001 Loss of CIG

" ON-131-002 PMS System Malfunction (SPD OP-1 31-002) PRIMARY CONTAINMENT:

" ON-147-001 Loss of FW Htg Extr Stm

ON-1 00-005 Excess DW Leakage

" ON-147-002 Loss of FW Htg String " ON-1 59-002 Containment Isolation

" ON-155-001 Control Rod Problems " ON-159-003 PC Water Level Anomaly

" ON-155-004 RPIS Failure MAIN GENERATOR:

" ON-155-007 Loss of CRD System Flow

ON-198-001 MVAR Cntl, Auto Volt Reg. Sync'd to Grid

" ON-156-001 Unexplained Reactivity Chg

" ON-198-002 MVAR Cntl, Manual Volt Reg. Sync'd to Grid

ON-164-002 Loss of Recirc Flow o ON-198-003 Mn Gen Connected Single Phase to Grid @ S/U

" ON-164-003 Recirc Pp Dual Seal Failure

" ON-198-004 Mn Gen Unable to Disco. from Grid After a iT

ON-178-002 Core Flux Oscillations

" ON-193-001 Turb EHC Malfunction RPV LEVEL:

ON-145-001 RPV Lvl Cntrl Malfunction ELECTRICAL:

ON-145-004 RPV Water Level Anomaly

ON-003-001 Loss of SUB 10 " ON-144-001 Emergency Operation of Condensate System

ON-003-002 Loss of SUB 20 HVAC:

ON-004-002 Energizing Dead 4KV Bus

ON-030-002 Loss of CS HVAC

ON-024-001 DIG Trip

ON-134-002 High/Low RX Bldg DP

ON-102-610 Loss of 125 VDC Bus 1D610 o ON-102-620 Loss of 125 VDC Bus 1D620 RADIATION:

ON-102-630 Loss of 125 VDC Bus 1D630 " ON-069-001 Abnormal Rad Rel - Liquid

ON-102-640 Loss of 125 VDC Bus 1D640 " ON-070-001 Abnormal Gas Rad Rel/CAM Alarms

ON-103-001 Grid Instabilities " ON-1 79-001 Increasing Offgas MSL Rad Levels

ON-103-003 Aux Buses 11 A/B Loss/UV Shed

ON-104-001 LOOP - U1 Response FUEL:

ON-104-201 Loss of 4KV Bus 1A (1A201) " ON-081-001 Fuel Handling Accident

ON-1 04-202 " ON-081-002 Refueling Platform Operation Anomaly Loss of 4KV Bus 1 B (1A202)

ON-104-203 Loss of 4KV Bus 1C (1A203) FIRE/FLOOD:

ON-104-204 Loss of 4KV Bus 1D (1A204) " ON-013-001 Fire

ON-117-001 Loss of Instrument Bus

ON-169-001 TB Flooding

ON-175-001 Loss of 24 VDC Bus

ON-169-002 RB Flooding

ON-188-001 Loss of 250 VDC Bus WEATHER:

COOLING:

ON-000-002 Natural Phenomena

" ON-009-001 Loss of RWMU " GO-100-014 Unit 1 Hot Weather

" ON-030-001 Loss of CS Chilled Water MISCELLANEOUS:

" ON-054-001 Loss of ESW

ON-000-01 0 Security Event

ON-1 11-001 Loss of Service Water

ON-037-001 Loss of Condensate Transfer

" ON-1 14-001 Loss of RBCCW " ON-089-001 Dry Fuel Storage Temp Anomaly

ON- 115-001 Loss of TBCCW " ON-100-003 Chemistry Anomaly

ON-133-001 Loss of TBCW

ON-100-009 Control Rm Evacuation

" ON-134-001 Loss of RBCW " ON-144-002 Condensate Filtr Anomaly

" ON-135-001 Loss of FPC/Coolant Inventory

" ON-142-003 Cooling Tower Screen Plugging

" ON-149-001 Loss of SDC

" ON-197-001 Loss of Stator Cooling Page 1 of 1

For Information Only Attachment F UNIT 2 OI-TA-008 OFF NORMAL PROCEDURES Revision 12 Page 21 of 25 SCRAM/TRIP: CONDENSER/VACUUM:

" ON-200-101 SCRAM, SCRAM Imminent

ON-242-001 Circ Water System Leak

" ON-258-001 Loss of RPS

ON-243-001 Main Condenser Vacuum & Offgas Sys Off

" ON-293-002 Main Turb Trip Normal Operation

" ON-283-001 Stuck Open SRV " ON-272-002 Hi HI H2 Concentration in Unit 2 Offgas RCB

" ON-284-001 MS Line Isol & Quick Recovery Discharge CIG/INSTRUMENT AIR:

REACTIVITY:

ON-218-001 Loss of Instrument Air

" ON-200-004 Rx Power > Authorized Limit " ON-225-001 Loss of CIG

ON-200-006 Loss of Reactor Heat Balance Calculation PRIMARY CONTAINMENT:

I

ON-231-002 PMS System Malfunction (SPM OP-231-002)

ON-247-001 Loss of FW Htg Extr Stm ON-200-005 Excess DW Leakage ON-259-002 Containment Isolation

ON-259-003 PC Water Level Anomaly

" ON-247-002 Loss of FW Htg String

ON-255-001 Control Rod Problems MAIN GENERATOR:

ON-298-001 MVAR Cntl, Auto Volt Reg. Sync'd to Grid

" ON-255-004 RPIS Failure

ON-255-007 Loss of CRD System Flow

ON-298-002 MVAR CntU, Manual Volt Reg. Sync'd to Grid

" ON-256-001 Unexplained Reactivity Chg " ON-298-003 Mn Gen Connected Single Phase to Grid @ S/U

" ON-298-004 Mn Gen Unable to Disco. from Grid After a TT

ON-264-002 Loss of Recirc Flow

ON-264-003 Recirc Pp Dual Seal Failure RPV LEVEL:

ON-278-002 Core Flux Oscillations

ON-245-001 RPV Lvl Cntrl Malfunction

" ON-293-001 Turb EHC Malfunction " ON-245-004 RPV Water Level Anomaly

" ON-244-001 Emergency Operation of Condensate System ELECTRICAL:

" ON-202-610 Loss of 125 VDC Bus 20610 HVAC:

" ON-202-620 Loss of 125 VDC Bus 2D620

ON-234-002 High/Low RX Bldg DP

ON-202-630 Loss of 125 VDC Bus 2D630 RADIATION:

ON-202-640 Loss of 125 VDC Bus 2D640

ON-279-001 Increasing Offgas MSL Rad Levels

ON-203-001 Grid Instabilities

ON-203-003 Aux Buses 11 A/B Loss/UV Shed FIREIFLOOD:

" ON-204-001 LOOP - U2 Response

ON-269-001 TB Flooding

" ON-204-201 Loss of 4KV Bus 1 A (2A201)

ON-269-002 RB Flooding

ON-204-202 Loss of 4KV Bus 1 B (2A202) WEATHER:

" ON-204-203 Loss of 4KV Bus 1C (2A203) o GO-200-014 Unit 2 Hot Weather

ON-204-204 Loss of 4KV Bus 1D (2A204)

" ON-217-001 Loss of Instrument Bus MISCELLANEOUS:

" ON-275-001 Loss of 24 VDC Bus

ON-200-003 Chemistry Anomaly

" ON-288-001 Loss of 250 VDC Bus

ON-200-009 Control Rm Evacuation

ON-244-002 Condensate Filtr Anomaly COOLING:

ON-21 1-001 Loss of Service Water

ON-214-001 Loss of RBCCW

" ON-215-001 Loss of TBCCW

" ON-233-001 Loss of TBCW

" ON-234-001 Loss of RBCW

ON-235-001 Loss of FPC/Coolant Inventory

ON-242-003 Cooling Tower Screen Plugging

ON-249-001 Loss of SDC

ON-297-001 Loss of Stator Cooling Page 1 of 1

For Information Only Attachment G OI-TA-008 UNIT 1 RPV STEAM DRYER Revision 12 STRUCTURAL INTEGRITY MONITORING Page 22 of 25 NOTE: The requirements of this instruction are applicable for MODE 1 only, and may be terminated when in MODES 2,3,4,5,* or DEFUELED.

Moisture Carryover Monitoring CH-SY-026, Moisture Carry Over Fraction (performed by Chemistry weekly) (To be performed daily following a transient event that could affect the dryer)

Parameters To Be Monitored For Steam Dryer Structural Integqrity At Least Daily At Rated Conditions

1. NBA01 Core Thermal Power

2. Condensing Chamber XY-B21-1 D002

a. NFP03 RPV Wide Range Press

b. NFL04 Rx Upset Range Lvl 517"variable tap

c. NFL05 RPV Extended Range Lvl 366" variable tap

3. Condensing Chamber XY-B21 -1 DOO4A

a. NFP05 RPV Wide Range Press

b. NFLO2 Rx Narrow Range Lvl B 517" variabletap

c. NBLO5 RPV Wide Range Lvl 366" variabletap

4. Condensing Chamber XY-B21-1D004B

a. NFP51 Reactor PressureSRU 4

b. NFL03 Rx Narrow Range Lvl C 517" variabletap

c. NBLO6 RPV Wide Range Lvi 366" variabletap

5. Condensing Chamber XY-1 4202

a. NFL07 RPV Extended Range Lvl 366" variabletap

6. FPA02 NSSS Total Feedwater Flow

7. NFF01 Rx Stm Flow A

8. NFF02 Rx Stm Flow B

9. NFF03 Rx Stm Flow C

10. NFF04 Rx Stm Flow D Page 1 of 1

For Information Only Attachment H OI-TA-008 UNIT 2 RPV STEAM DRYER Revision 12 STRUCTURAL INTEGRITY MONITORING Page 23 of 25 NOTE: The requirements of this instruction are applicable for MODE 1 only, and may be terminated when in MODES 2,3,4,5,* or DEFUELED.

Moisture Carryover Monitorinq CH-SY-026, Moisture Carry Over Fraction (performed by Chemistry weekly) (To be performed daily following a transient event that could affect the dryer)

Parameters To Be Monitored For Steam Dryer Structural Integrity At Least Daily At Rated Conditions

1. NBA01 Core Thermal Power

2. Condensing Chamber XY-B21-2D002

a. NFP03 RPV Wide Range Press

b. NFL04 Rx Upset Range Lvi 517"variable tap

c. NFL05 RPV Extended Range Lvi 366" variable tap

3. Condensing Chamber XY-B21-2D004A

a. NFP05 RPV Wide Range Press

b. NFL02 Rx Narrow Range Lvl B 517" variable tap

c. NBLO5 RPV Wide Range Lvl 366" variable tap

4. Condensing Chamber XY-B21-2D004B

a. NFP51 Reactor Pressure SRU 4 b, NFL03 Rx Narrow Range Lvi C 517" variable tap

c. NBL06 RPV Wide Range Lvi 366" variable tap

5. Condensing Chamber XY-24202

a. NFL07 RPV Extended Range Lvl 366" variable tap

6. FPA02 NSSS Total Feedwater Flow

7. NFF01 Rx Stm Flow A

8. NFF02 Rx Stm Flow B

9. NFF03 Rx Stm Flow C

10. NFF04 Rx Stm Flow D Page 1 of 1

For Information Only Attachment I UNIT 1 AND UNIT 2 RPV STEAM DRYER 01-TA-008 STRUCTURAL INTEGRITY MONITORING Revision 12 Page 24 of 25

Background

GE SIL No 644 Rev 2 recommends monitoring on a daily basis for significant anomalies (such as step changes in indicated values) that may indicate a steam dryer failure. The following observations can indicate a problem with the steam dryer:

Step change in reactor pressure (usually small -2 to 3 psi)

Step change in reactor level (-2 inches)

Step change in steamline flow (-5%)

Therefore, trend plots of RPV parameter data will be useful for performing the monitoring.

Significant steam dryer damage could be detected by a change in steam line fltow distribution.

Damage to the dryer skirt or hood in the region of the reference leg vessel tap could permit flow through the annular area around the skirt. In the presence of the vessel level reference level instrumentation this flow has the potential to induce a Bernoulli effect indication error that may affect both the water level and reactor pressure indications.

GE SIL No 644 Rev 2 recommends monitoring moisture content in the steam leaving the reactor weekly. The Chemistry department normally performs CH-SY-026, Moisture Carry Over Fraction on a monthly basis. During the first cycle of operation with a new dryer, the Chemistry department is planning to perform the analysis weekly for at least the first year if not the whole cycle.

Following a transient event that may result in pressure loading of the steam dryer (relief valve opening, turbine stop valve closure, etc), monitor moisture content daily until the structural integrity of the dryer is confirmed. Once it has been established that the dryer sustained no damage, routine monitoring may be resumed. The Chemistry department will have to be notified to perform daily moisture content sampling following a transient that has caused pressure loading of the dryer. OP-AD-327, Post Reactor Transient / Scram / Shutdown Evaluation will ensure CH-SY-026 is performed daily until parameters confirm that there is no compromise to the steam dryer structural integrity.

Moisture content can change during the operating cycle due to changes in core power, core flow, or core radial peaking. An observed moisture carryover of 0.2% would be a significant change for an efficient dryer with a normal carryover of about 0.05%. A high core radial peaking factor has the capability to overload a local section of the steam separator which would overload a local section of the steam dryer. A structural failure would allow wet steam to bypass the dryer vane banks. An increase in feed-to-steam 'flow mismatch may validate an increase in moisture carryover. Moisture carryover can affect turbine efficiency and increase balance of plant radiation levels.

Page 1 of 2

For Information Only Attachment I UNIT 1 AND UNIT 2 RPV STEAM DRYER O-TA-008 STRUCTURAL INTEGRITY MONITORING Revision 12 Page 25 of 25 References

1. GE SIL No. 644 Rev 2 BWR Steam Dryer Integrity

2. GE SIL No. 644 Supplement 1 BWR Steam Dryer Integrity

3. EC 674923 - EPU - Steam Dryer Upgrade - Unit 1

4. ON-145-004, RPV Water Level Anomaly

5. TRM 2.2, Instrument Trip Setpoint Table

6. TM-OP-062-ST, Reactor Vessel and Internals

7. TM-OP-080-ST, Reactor Vessel Instrumentation

8. P&ID M-142 sheet 1 Page 2 of 2

PLA-6506, Submittal of Startup Test Procedures

Contents

Text

References:

Attachment:

SUMMARY

Purpose:

SUMMARY

SUMMARY

Background

Navigation menu

PLA-6506, Submittal of Startup Test Procedures

Text

References:

Attachment:

SUMMARY

Purpose:

SUMMARY

SUMMARY

Background

Navigation menu

Search