Text

Transmittal of Startup Test Procedures Pursuant to License Conditions 2.C. (36) (B) 8 and 2.C. (36) (C)
	ML081220236
Person / Time
Site:	Susquehanna
Issue date:	04/21/2008
From:	Mckinney B; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PLA-6351, TP-199-009, Rev 1
	Download: ML081220236 (133)
	v • d • e

Brltt T. McKlInney Sr. Vice President & Chief Nuclear Officer APR 2 12008 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com ppx a..*TM U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 OPERATING LICENSE NO. NPF-14 LICENSE CONDITIONS 2.C. (36) (b) 8 and 2.C. (36) (c)

PLA-6351 Docket Nos. 50-387 and 50-388 Reference.

1) PLA-6332, B.T. McKinney (PPL) to Document Control Desk (NRC),

"Susquehanna Steam Electric Station Unit 1 Operating License No. NPF-14 License Condition 2. C. (36) (B) 1, "dated February 23, 2008.

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

License Condition 2.C. (36) (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, before initial power ascension above 3489 MWt."

Reference 1 provided the methodology for updating the limit curves required by this License Condition. TP-162-030 "Steam Dryer and Flow Induced Vibration Testing" is the flow-induced vibration related CPPU startup test procedure and is provided herein.

License Condition 2.C. (36) (c) requires:

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

(1) steam dryer strain gauge acceptance criteria to be used up to 107% of CLTP and the MSL strain gauge limit curves to be applied for evaluating steam dryer performance above 107% 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; Document Control Desk PLA-6351 (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."

Reference 1 provided the acceptance criteria described in item (1) of this License Condition. TP-162-030 includes the acceptance criteria by reference.

The following three procedures provided herein collectively include the topics required by this License Condition.

TP-199-009 - "Extended Power Uprate Master Procedure, Special, Infrequent, or Complex Test/Evolution (SICT/E)".

TP-162-030 - "Steam Dryer and Flow Induced Vibration Testing".

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

If you have any questions or require additional-information, please contact Mr. Michael H. Crowthers at (610) 774-7766.

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

Executed on:

/

B. T. McKinney : Startup Test Procedures Document Control Desk PLA-6351 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 to PLA-6351 Startup Test Procedures

For Information Only PROCEDURE COVERýSHEET PPL SUSQUEHANNA, LLC PROCEDURE EXTENDED POWER UPRATE MASTER TEST PROCEDURE TP-199-009 SPECIAL, INFREQUENT OR COMPLEX TEST/EVOLUTION Revision 1 (SICT/E)

Page 1 of 81 ADHERENCE LEVEL: STEP-BY-STEP QUALITY CLASSIFICATION:

APPROVAL CLASSIFICATION:

(X)

QA Program

( ) Non-QA Program (X)

Plant

( ) Non-Plant

( )

Instruction EFFECTIVE DATE:

O/A; PERIODIC REVIEW FREQUENCY:

NIA 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)

TP-1 99-009 Revision 1 Page 2 of 81 PROCEDURE REVISION

SUMMARY

TITLE:

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

1)

Added Attachment Y, Z, and AA that are enhancements for ensuring steam dryer and piping flow induced vibration testing is properly performed.

2)

Revised steps within Section 7 to reflect Attachments Y, Z, and AA.

3)

Added place keeping blocks to Attachment X.

4)

Deleted requirement to record and analyze strain gauge data with zero excitation as such data would not be useable.

5)

Made other clarifications.

TP-1 99-009 Revision 1 Page 3 of 81 TABLE OF CONTENTS SECTION PAGE

1.

PURPOSE/SCOPE 6

2.

DISCUSSION 6

3.

REFERENCES 8

4.

TEST EQUIPMENT 10

5.

PRECAUTIONS/NOTES 10

6.

PREREQUISITES 11

7.

PROCEDURE 12 7.1 Test Condition A Testing 12 7.2 START OF SICT/E SECTION. MELLLA TEST CONDITION A 16 7.3 Test Condition B Testing 17 7.4 Test Condition C 18 7.5 MELLLA Test Condition B 19 7.6 Preparation for Power Ascension Above 3489 MWt (88.2%)

22 7.7 (Start of SICT/E Section) Initial power ascension above 3489 MWt.

24 7.8 Test Condition D Testing 25 7.9 Preparation for Power Ascension Above 3611 MWt (91.3%)

26 7.10 (Start of SICT/E Section) Initial power ascension above 3611 MWt (91.3%).

28 7.11 Test Condition E Testing 29

8.

RESTORATION 30

9.

ACCEPTANCE CRITERIA 30

10.

REVIEW 31

11.

RECORDS 31

TP-199-009 Revision 1 Page 4 of 81 ATTACHMENTS ATTACHMENT A

B C

D E

F G

H I

J K

L M

N 0

P 0

R S

T U

Test Control Documentation EPU Test 42 - Required I&C Surveillances Test Condition A Review Summary EPU and MELLLA Test Condition Definitions Test Condition B Review Summary Test Condition C Review Summary ST-1 B Moisture Carryover Testing Unit 1 Station Verification of Activities for ascending above 3489 MWt, Test Condition D Review Summary Unit 1 Station Verification of Activities for ascending above 3648 MWt.

Test Condition E Review Summary ST-12B RBM Testing ST-12A APRM Testing - Test Condition A ST-i 9 Core Performance Testing Test Plateau Review Record ST-12A APRM Testing - Non-Test Condition A Final Test Program Review Record TP-199-009 Subtest Numbers ST-1A Chemical and Radiochemical ST-10 IRM Performance ST-2 Radiation Measurements PAGE 32 33 35 37 38 39 41 42 43 44 45 47 48 49 50 51 52 53 56 57 58

TP-1 99-009 Revision 1 Page 5 of 81 ATTACHMENTS ATTACHMENT V

W x

Y z

AA ST-22 Pressure Regulator ST-24 Turbine Valve Surveillance Initial Power Ascension to 77% power Initial Power Ascension to 88% power Initial Power Ascension to 91 % power and Test Condition D Steady State Vibration Testing Initial Power Ascension to 94% power and Test Condition E Vibration Testing PAGE 59 61 62 73 75 77

TP-199-009 Revision 1 Page 6 of 81

1.

PURPOSE/SCOPE The purpose of this procedure is to provide a centralized mechanism for documenting completion of all items necessary to perform a successful Unit 1 Phase 1 Extended Power Uprate Test Program, and to ensure that all testing required by our submittal to the NRC for the confirmation of acceptable plant performance in MELLLA (Maximum Extended Load Line Limit Analysis) operation conditions is successfully completed at the proper test conditions. 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 1 Phase 1 Extended Power Uprate Test Program.

2.3 In compliance and in conjunction with NDAP-OA-0406, this procedure imposes Administrative Controls throughout the EPU Test Program to direct reactor startup, power escalation and the establishment of Test Conditions.

2.4 A Test Condition (TC) is a defined range of reactor power and core flow conditions at which testing is conducted. The Test Condition also includes the startup path to those ranges. The Test Conditions for the Unit 1 Phase 1 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 not to exceed the ELLLA line. (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 not to exceed the ELLLA line.

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 not to exceed the ELLLA line.

TP-199-009 Revision 1 Page 7 of 81 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.

2.4.6 MELLLA TC A - Reactor power between +0% and -5% power of the MELLLA Boundary that extends from the 50% core flow line to the core flow line that results in 3140 MWt (79.4%) on the MELLLA Boundary. (Percent reactor core flow is specified in percent of 100 Mlb/hr throughout this procedure.)

2.4.7 MELLLA TC B - Reactor power between +0% and -5% power of the MELLLA Boundary and between 3314 MWt (83.8%) and 3489 MWt (88.2%).

2.5 A Test Plateau is an administrative grouping of one or more Test Conditions and/or plant conditions to support efficient control of test scheduling, results review and power escalation. The Test Plateaus for the Unit 1 Phase 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, TC C, MELLLA TC A and MELLLA TC B.

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 Appendices C, E, F, I and K specify the minimum tests that are required to be implemented in TC A and MELLLA TC A, TC B, TC C and MELLLA TC B, TC D and TC E, respectively. The EPU Subtest number specified in these attachments has the format of xy.z where:

2.6.1 xy is the 'Test Number" specified in the test specification. x is a one or two digit number and is always present. y is an alphabetical character and is optional.

2.6.2 z is an arbitrary number used to distinguish specific partial implementations of the test xy when the test as specified in the test specification is not fully implemented in a Test Condition, or when more than one implementing procedure is required.

TP-199-009 Revision 1 Page 8 of 81 2.7 M-1 563 test specifications for Test 33 "Piping Steady State Vibration" and Test 100 "Main Steam and Feedwater Piping Vibration" overlap with each other. To clarify pipe vibration testing, Test 100 contains all testing required in M-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. It does, however, provide a method for ensuring that all testing within each Test Condition is completed and ensures that all required reviews and prerequisites are satisfied during the transition from one Test Condition to the next.

2.9 Those sections of this procedure that provide direction to enter into and perform tests in MELLLA TC A and MELLLA TC B, and to initially increase power beyond 3489 MWt are classified as SICT/Es as these sections represent an expansion of station operation beyond current bounds of existing procedures or training and intensified test and evolution controls are required. Those sections contain SICT/E in their heading

3.

REFERENCES 3.1 EC-PUPC-1 1005 ARTS/MELLLA Task Report T1005, Startup Test Specifications 3.2 GO-100-002, Plant Startup, Heatup, and Power Operation 3.3 EC 730177 SIP0725 3.4 NDAP-QA-0320 "Special, Infrequent or Complex Test/Evolutions" 3.5 NDAP-QA-0008 3.6 CH-SY-026 Moisture Carryover 3.7 TP-045-001 Feedwater Master Water Level Controller MWLC Tuneup (SICT/E) 3.8 TP-164-031, Core Flow Calibration 3.9 TP-164-036, Reactor Recirc Flow Control for MELLLA (SICT/E) 3.10 SR-178-012, LPRM Calibration Validation 3.11 M-1563, Nuclear Engineering Specification for Extended Power Uprate Startup Testing 3.12 NDAP-QA-0406, Extended Power Uprate Test Program

TP-199-009 Revision 1 Page 9 of 81 3.13 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.

3.14 PLA-6242, "Susquehanna Steam Electric Station Proposed License Amendment No. 285 for Unit 1 Operating License No. NPF-14 and Proposed License Amendment No. 253 for Unit 2 Operating License No. NPF-22 Extended Power Uprate Application Regarding Steam Dryer and Flow Effects Request For Additional Information Responses."

3.15 GE-NE-0000-0029-7418 3.16 GE 26A7374 "Dryer Vibration Measurement Test Specification" 3.17 TP-055-006 "CRD Stroke Time and Friction Measurement" 3.18 TP-193-041 "EPU EHC Pressure Regulator Testing" 3.19 SO-1 00-007 "Daily Surveillance Operating Log" 3.20 NDAP-OA-0450 "Extended Power Uprate Project Implementation" 3.21 RE-081-036 "Core Fuel Pool Verification" 3.22 RE-OTP-201 'TIlP Uncertainty" 3.23 SC-133-101 "U1 TB Vent Weekly Iodine & Particulate Activity" 3.24 SC-133-102 "U1 TB Vent Monthly Tritium & Grab Sample Analysis" 3.25 SC-143-101 "U1 TB Condenser Air Ejector Monthly Noble Gas" 3.26 SC-176-101 "U1 Rx Coolant Conductivity Determination" 3.27 SC-176-103 "U1 Rx Coolant Gross Beta and Gamma Activity" 3.28 SC-176-106 "U1 Rx Coolant Chloride and pH Determination" 3.29 SE-178-001 "APRM 1 Drive Flow Calibration" 3.30 SE-178-002 "APRM 2 Drive Flow Calibration" 3.31 SE-1 78-003 "APRM 3 Drive Flow Calibration" 3.32 SE-1 78-004 "APRM 4 Drive Flow Calibration" 3.33 SI-164-305 "Recirc MG Set Positioners High Speed Stops"

TP-199-009 Revision 1 Page 10 of 81 3.34 SR-1 00-008 "In Sequence Critical and Shutdown Margin Demo."

3.35 SR-1 55-004 "Scram Time Measurements of Control Rods" 3.36 TP-144-048 "Condensate Pump Trip" 3.37 TP-1 62-030 "Steam Dryer Vibration Testing" 3.38 TP-1 00-013 "EPU Data Collection and Extrapolation" 3.39 SSES Unit 1 Operating License NPF-1 4 Amendment 246

4.

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

5.

PRECAUTIONS/NOTES 5.1 Sections and steps within sections must be completed in the order listed unless otherwise specified.

5.2 Tests identified in the Test Condition Review Summary Attachments may be completed in any order unless otherwise specified.

5.3 Per Operating License Condition 2.C. (36) (d), the following key attributes of the PATP 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.

TP-199-009 Revision 1 Page 11 of 81 5.4 Per Operating License Condition 2.C (36) (a) 4, "if any" strain gauge data exceeds Level 1 'acceptance criterion for steam dryer strains at each 3.5%

power ascension step up to 107% of 3489 MWt or frequency peak from the MSL strain gauge data exceeds the limit curve for the MSL strains above 107% of 3489 MWt, PPL shall return the facility to a power level at which the acceptance criterion is not exceeded. PPL shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC Staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power." Italicized words are those added by the TP author. As of 2/22108, PPL is waiting on clarification from the NRC on this Condition.

5.5 Per Operating License Condition 2.C (37) (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 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 condensate 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 failure 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.

6.

PREREQUISITES NOTE:

Steps within the PREREQUISITES section may be completed in any order.

fJ 6.1 Attach AND Complete SICT/E Analysis, Form NDAP-QA-0320-1, for this TP.

Confirmed By Date EJ 6.2 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: Mode 2 may not be entered until this Administrative Hold Condition is lifted by step 7.1.7 in this TP or as otherwise notified by the Vice President-Nuclear Operations. Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date

TP-1 99-009 Revision 1 Page 12 of 81

7.

PROCEDURE NOTE (1):

Sections and steps within sections must be completed in the order listed unless otherwise specified.

NOTE (2):

Tests identified in an Attachment may be completed in any order unless otherwise specified.

7.1 Test Condition A Testing EJ 7.1.1 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

7.1.2 Perform tests listed in Attachment C that are specified for Mode 5 and Mode 4.

NOTE:

Steps 7.1.3 through 7.1.6 may be completed in any order.

7.1.3 Confirm the following:

O

a.

All testing listed in Attachment C with additional plant condition requirements of Mode 4 or Mode 5 with the exception of ST 5.2 has been successfully completed OR Test Exception Reports have been written. ST 5.2 may be completed anytime prior to exceeding 1580 MWt (40%).

Ol

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 dispositioned.

O

d.

There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Mode 2.

Confirmed By Date EPU Test Program Director

TP-199-009 Revision 1 Page 13 of 81 Confirm that Partial 1 of EC 690275 "Extended Power Uprate Implementation Phase I" is closed.

El 7.1.4 Confirmed By Date 11 7.1.5 Confirm that all items in GO-1 00-002 Attachment A "Unit 1 Station Verification of Activities for Entering Mode 2" have been signed off.

Confirmed By Shift Supervision Date 7.1.6 El Permission is granted to:

a.

enter Mode 2.

b.

increase reactor thermal power with plant conditions 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 approved test procedures.

c.

perform all remaining tests listed in Attachment C.

d.

Perform all tests listed in Attachments E and F.

El El1 VP - Nuclear Operation

/

Date El 7.1.7 Inform Shift Supervision that the Administrative Hold Condition described in step 6.2 concerning not entering Mode 2 is lifted.

Confirm that the associated ZWO has been closed.

/

Confirmed By Shift Supervision Date

TP-199-009 Revision 1 Page 14 of 81 E]

7.1.8 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: MELLLA Test Condition A as defined in Attachment D shall not be entered until this Administrative Hold Condition is lifted by step 7.2.2 in this TP or as otherwise notified by the Vice President-Nuclear Operations.

Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date Shift Supervision O

7.1.9 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: The plant may not operate above the ELLLA Boundary as defined in the Unit 1 Power / Flow Map until this Administrative Hold Condition is lifted by step 7.5.9 in this TP or as otherwise notified by the Vice President-Nuclear Operations. Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date Shift Supervision El 7.1.10 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: MELLLA Test Condition B as defined in Attachment D shall not be entered until this Administrative Hold Condition is lifted by step 7.5.10 in this TP or as otherwise notified by the Vice President-Nuclear Operations.

Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date Shift Supervision

TP-199-009 Revision 1 Page 15 of 81 0

7.1.11 Confirm that Shift Supervision is aware of the following 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. Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date Shift Supervision O

7.1.12 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

7.1.13 Enter Mode 2 and Perform remaining tests listed in Attachment C following instructions provided in Attachment X.

O 7.1.14 Confirm by review of Attachment C that the following tests have been successfully completed OR Test Exception Reports have been written and dispositioned.

EPU Subtest 11 at 72.7%

EPU Subtest 12A.2 at 72.7%

EPU Subtest 12B EPU Subtest 19 at 72.7%

Confirmed By Date

TP-1 99-009 Revision 1 Page 16 of 81 Confirm that feedwater level control tuneups per TP-045-001 have been completed to the extent necessary to support Reactor Recirculation flow control testing as specified in TP-164-036 "Reactor Recirc Flow Control for MELLLA".

El 7.1.15

/

Confirmed By Station Engineering Date 11 7.1.16 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 TP-1 64-036 "Reactor Recirc Flow Control for MELLLA" in MELLLA Test Condition A.

Confirmed By Reactor Engineering

/

Date El 7.1.17 Permission is granted to operate the plant at conditions defined as MELLLA Test Condition A in Attachment D not to exceed the MELLLA Boundary or the ELLLA Boundary, whichever is less, AND to continue testing as specified in this procedure.

/

Granted By VP-Nuclear Operations Date 7.2 START OF SICT/E SECTION. MELLLA TEST CONDITION A 7.2.1 Confirm that SICT/E Briefing is complete AND that Form NDAP-QA-0320-2 has been signed by the briefers.

0]

/

Confirmed By Date 7.2.2 Inform Shift Supervision that the Administrative Hold Condition described in step 7.1.8 concerning entering MELLLA Test Condition A is lifted. Confirm that the associated ZWO has been closed.

/

Confirmed By Shift Supervision Date

TP-199-009 Revision 1 Page 17 of 81 EJ 7.2.3 Inform Shift Supervision to Establish reactor conditions within those defined as MELLLA Test Condition A in Attachment D.

O 7.2.4 Perform tests listed in Attachment C that are specified for MELLLA TC A.

0 7.2.5 END OF SICT/E SECTION.

7.2.6 Confirm the following:

O

a.

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

O

b.

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

o

c.

All Test Exception Reports have been dispositioned.

O

d.

There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition B.

Confirmed By Date EPU Test Program Director 7.3 Test Condition B Testing O

7.3.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition B in Attachment D.

7.3.2 Confirm that Shift Supervision is aware that all tests listed 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 1:1 7.3.3 Perform tests listed in Attachment E.

TP-1 99-009 Revision 1 Page 18 of 81 7.3.4 Confirm the following:

O

a.

All testing listed in Attachment E 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 E have been reviewed by the Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written.

o

c.

All Test Exception Reports have been dispositioned.

EO

d.

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

Confirmed By Date EPU Test Program Director NOTE:

Sections 7.4 and 7.5 can be performed in parallel.

7.4 Test Condition C Ol 7.4.1 Confirm that Shift Supervision is aware that reactor power cannot exceed 3489 MWt (88%) until the current Administrative Hold Condition imposed by step 7.1.11 is lifted in step 7.7.2. Reactor thermal power may briefly exceed 3489 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date Shift Supervision O

7.4.2 Confirm that Shift Supervision is aware that all tests listed in Attachment F can be performed in any order at reactor conditions within those defined as EPU Test Condition C in Attachment D or at lower power levels as specified in Attachment F.

Confirmed By Date Shift Supervision O

7.4.3 Perform TP-1 99-009 Attachment Y, Initial Power Ascension to 88% Power.

TP-1 99-009 Revision 1 Page 19 of 81 E5 7.4.4 Request Reactor Engineering to Determine if an 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.

O 7.4.5 Perform tests listed in Attachment F except for those specified for MELLLA TC B.

7.4.6 Confirm the following:

5

a.

All testing listed in Attachment F 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 F have been reviewed by the Shift Test Coordinator or EPU Test Program Director OR Test Exception Reports have been written.

[]

c.

All Test Exception Reports have been dispositioned.

Confirmed By Date EPU Test Program Director El 7.4.7 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.

7.5 MELLLA Test Condition B 5

7.5.1 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: The plant may not operate above the ELLLA Boundary as defined in the Unit 1 Power / Flow Map until this Administrative Hold Condition is lifted by step 7.5.9 in this TP or as otherwise notified by the Vice President-Nuclear Operations.

Confirmed By Date Shift Supervision

TP-1 99-009 Revision 1 Page 20 of 81

[]

7.5.2 Confirm that Shift Supervision is aware of the following Administrative Hold Condition: MELLLA Test Condition B as defined in Attachment D shall not be entered until this Administrative Hold Condition is lifted by step 7.5.10 in this TP or as otherwise notified by the Vice President-Nuclear Operations.

Confirmed By Date Shift Supervision O

7.5.3 Confirm by review of Attachment F that the following tests have been successfully completed OR Test Exception Reports have been written and dispositioned.

EPU Subtest 11 EPU Subtest 12A.2 EPU Subtest 19 prior to MELLA TC B EPU Subtest 23 EPU Subtest 35 100 Mlb/hr prior to MELLA TC B Confirmed By Date 13 7.5.4 Confirm that 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 MELLLA Test Condition B.

Confirmed By Date EPU Test Program Director El 7.5.5 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 TP-164-036 "Reactor Recirc Flow Control for MELLLA" in MELLLA Test Condition B.

Confirmed By Date Reactor Engineering

TP-199-009 Revision 1 Page 21 of 81 O

7.5.6 Permission is granted to operate the plant at conditions defined as MELLLA Test Condition B in Attachment D not to exceed the MELLLA Boundary or 3489 MWt AND to continue testing as specified in this procedure.

Granted By Date VP-Nuclear Operations o

7.5.7 START OF SICT/E SECTION.

o 7.5.8 Confirm that SICT/E Briefing is complete AND that Form NDAP-QA-0320-2 has been signed by the briefers.

Confirmed By Date o

7.5.9 Inform Shift Supervision that the Administrative Hold Condition described in step 7.1.9 concerning operating above the ELLLA Boundary is lifted. Confirm that the associated ZWO has been closed.

Confirmed By Date 0

7.5.10 Inform Shift Supervision that the Administrative Hold Condition described in step 7.1.10 concerning entering MELLLA Test Condition B is lifted. Confirm that the associated ZWO has been closed.

Confirmed By Date El 7.5.11 Inform Shift Supervision to Establish reactor conditions within those defined as MELLLA Test Condition B in Attachment D.

0 7.5.12 Perform tests listed in Attachment F that are specified for MELLLA TC B.

7.5.13 Confirm the following:

Ol

a.

All testing listed in Attachment F for MELLLA Test Condition B has been successfully completed OR Test Exception Reports have been written.

TP-199-009 Revision 1 Page 22 of 81 El

b.

All EPU Test Results Summaries for completed Startup Tests listed in Attachment F for MELLLA Test Condition B 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 written against MELLLA Test Condition B tests have been dispositioned.

Confirmed By Date EPU Test Program Director O

7.5.14 END OF SICT/E SECTION.

O 7.5.15 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition C in Attachment D.

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

NOTE:

Steps 7.6.1 through 7.6.9 may be completed in any order.

0 7.6.1 Confirm that all CRs and CRAs necessary for power ascension above 3489 MWt (88%) up to a maximum of 3611 MWt (91.3%)

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

Confirmed By Date Manager - Corrective Action and Assessment O

7.6.2 Confirm that Partial 2 of EC 690275 "Extended Power Uprate Implementation Phase I" is closed.

Confirmed By Date

TP-1 99-009 Revision 1 Page 23 of 81 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.(36)(b)1.

5

a.

Date information was provided to NRC.

5

b.

Line a plus 45 days.

Confirmed By Date 5

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.(36)(b)8.

Confirmed By Date 7.6.5 Confirm that PPL has notified the NRC project manager that all appropriate actions required to assure consistency between the CPPU containment analysis and SSES Unit 1 and Unit 2 operating and emergency procedures have been completed as required by License Condition 2.C.(39).

Confirmed By Date 7.6.6 Confirm the following:.

5

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%).

5

b.

There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition D.

Confirmed By Date EPU Test Program Director 5l 7.6.7 Complete Attachment H, "Unit 1 Station Verification of Activities for ascending above 3489 MWt".

TP-199-009 Revision 1 Page 24 of 81 Q

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.

Confirmed By Date Reactor Engineering 7.6.9 Permission is granted to:

O

a.

increase reactor thermal power with plant conditions not to exceed 3611 MWt (91.3%) or 108 Mlbm/Hr core flow.

Reactor thermal power may briefly exceed 3611 MWt during minor transients inherent to approved test procedures.

0

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.

O 7.7.1 Confirm that SICT/E Briefing is complete AND that Form NDAP-QA-0320-2 has been signed by the briefers.

Confirmed By Date O

7.7.2 Inform Shift Supervision that the Administrative Hold Condition described in step 7.1.11 concerning power operation above 3489 MWt (88.2%) is lifted. Confirm that the associated ZWO has been closed.

Confirmed By Date Shift Supervision

TP-199-009 Revision 1 Page 25 of 81 Q1 7.7.3 Confirm that Shift Supervision is aware of the following 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-Nuclear Operations. Reactor thermal power may briefly exceed 3611 MWt during minor transients inherent to approved test procedures. Record associated ZWO that has been added to the System Status File.

ZWO Number Confirmed By Date Shift Supervision O

7.7.4 Perform TP-199-009 Attachment Z Step 1 in its entirety.

Confirmed By Date O

7.7.5 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

7.7.6 Inform Shift Supervision to increase reactor power to 3611 MWt (91.3%).

O 7.7.7 (End of SICT/E Section) Confirm that reactor power is at 3611 MWt (91.3%).

Confirmed By Date 7.7.8 Perform TP-199-009 Attachment Z Step 2.

7.8 Test Condition D Testing O

7.8.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition D in Attachment D.

11 7.8.2 Perform testing listed in Attachment 1.

TP-199-009 Revision 1 Page 26 of 81 10 7.8.3 IF dryer strain gauge data exceeds any Level 1 acceptance criteria, THEN reduce power to a level at which the acceptance criteria are not exceeded.

7.8.4 Confirm the following:

O3

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 dispositioned.

Confirmed By Date EPU Test Program Director O

7.8.5 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.

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.

O 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

TP-1 99-009 Revision 1 Page 27 of 81 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.(36)(a)3.

Ql

a.

Date information was provided to NRC.

El

b.

Date and time that NRC Project Manager confirmed receipt of information E3

c.

Line b plus 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

Confirmed By Date 7.9.3 Confirm the following:

El

a.

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

El

b.

There are no open Test Exceptions or Subsequent Action items related to Test Exceptions that are required to be completed and closed prior to entering Test Condition E.

Confirmed By Date EPU Test Program Director El 7.9.4 Complete Attachment J, "Unit 1 Station Verification of Activities for ascending above 3611 MWt".

El 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.

Confirmed By Date Reactor Engineering 7.9.6 Permission is granted to:

El

a.

increase reactor thermal power with plant conditions not to exceed 3733 MWt.

TP-1 99-009 Revision 1 Page 28 of 81 0

b.

perform all tests listed in Attachment K.

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

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

Confirmed By Date 0

7.10.2 Inform Shift Supervision that the Administrative Hold Condition described in step 7.7.3 concerning power operation above 3611 MWt is lifted. Confirm that associated ZWO has been closed.

Confirmed By Date Shift Supervision E

7.10.3 Perform Attachment AA Step 1 in its entirety.

Confirmed By Date EO 7.10.4 Confirm that Shift Supervision is aware that all 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 O

7.10.5 Confirm that Shift Supervision is aware that ST-103 Condensate Pump Trip must be completed within 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months (14 days) of initially achieving 3733 MWt.

Confirmed By Date Shift Supervision Ol 7.10.6 Inform Shift Supervision to increase reactor power to 3733 MWt and establish reactor conditions within those defined as EPU Test Condition E in Attachment D.

TP-1 99-009 Revision 1 Page 29 of 81 O

7.10.7 (End of SICT/E Section) Record date and time when 3.733 MWt is initially achieved.

DATE TIME 7.11 Test Condition E Testing O

7.11.1 Calculate AND Record date and time by which ST-1 03 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 step 7.10.7.

DATE TIME o

7.11.2 Confirm that Shift Supervision is aware that ST-103 Condensate Pump Trip must be completed by the date and time recorded in step 7.11.1.

Confirmed By Date Shift Supervision O

7.11.3 Confirm that Shift Supervision is aware that reactor power cannot exceed 3489 (88.2%) MWt following ST-103 Condensate Pump Trip until test results have been analyzed and found to be acceptable.

Record associate ZWO that has been added to the system status file.

ZWO Number Confirmed By Date Shift Supervision O

7.11.4 Perform testing listed in Attachment K.

O 7.11.5 IF dryer strain gauge data exceeds any acceptance criteria, THEN reduce power to a level at which the acceptance criteria are not exceeded.

5 7.11.6 Enter date and time that ST-103 Condensate Pump Trip was performed. Confirm that test was performed prior to date and time listed in step 7.11.1 Confirmed By Date

TP-1 99-009 Revision 1 Page 30 of 81 EO 7.11.7 Confirm that ST-1 03 Condensate Pump Trip test results have been analyzed and found to be acceptable.

Confirmed By Date O

7.11.8 Confirm that Shift Supervision is aware that reactor power can be restored to 3733 MWt as ST-1 03 Condensate Pump Trip test results have been analyzed and found to be acceptable.

Confirmed By Date Shift Supervision 7.11.9 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 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 dispositioned.

O 7.11.10 Prepare a Test Plateau Review Record, Attachment G, 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 0, 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.

TP-1 99-009 Revision 1 Page 31 of 81

10.

REVIEW 10.1 Review of this procedure is complete.

/

Confirmed By Date

11.

RECORDS 11.1 Transmit completed TP to DCS.

/

Confirmed By Date

Attachment A TP-199-009 Revision 1 Page 32 of 81 TEST CONTROL DOCUMENTATION Procedure No. TP-199-009 Page of Page 1 of 1

Attachment B EPU TEST 42 TP-1 99-009 REQUIRED I&C SURVEILLANCES Revision 1 Page 33 of 81 Confirm that the following Surveillances or Work Items have been successfully completed during the U1-15RIO.

Instrument Description Surveillance Work Iten FISB21 1 N006A/B/C/D MSL Flow Channels SI-183-204 RTSV 833 FISB21 1 N007A/B/C/D SI-183-205 RTSV 833 FISB21 1 N008A/B/C/D SI-183-206 RTSV 874 FISB2I 1 N009A/B/C/D SI-183-207 RTSV 874 183 184 314 318 103 104 SI-183-304 SI-183-305 SI-183-306 SI-183-307 RTSV 977 RTSV 977 PSHC721 N003A,B,C,D PT-Cl 2-1 N054A/B PS-Cl 2-1 N654A/B FYC321 K603 APRM11 APRM12 APRM13 APRM 14 RBM 1A RBM 1B LTC411NO01 TSHLC41 1 N003 Main Turbine 1st Stage RPS Trip Pressure Switches U1 Turbine 1st Stage Pressure Transmitters and Switches Reactor Total Steam Flow Loop Calibration Functional Test of APRM 1 Calibration Test of APRM 1 Functional Test of APRM 2 Calibration Test of APRM 2 Functional Test of APRM 3 Calibration Test of APRM 3 Functional Test of APRM 4 Calibration Test of APRM 4 Calibration of RBM 1A Calibration of RBM 1 B SLC Storage Tank Level Calibrate TSHLC41 1 N003 Stby Liq Ctl Storage Tank N/A N/A N/A SI-178-251 SI-178-341 SI-178-252 SI-178-342 SI-178-253 SI-1 78-343 SI-178-254 SI-178-344 S1-178-355 SI-178-356 N/A N/A RTPM C4591-01 PCWO 779215 PCWO 865443 TP-1 78-043 TP-1 78-043 TP-178-043 TP-1 78-043 TP-1 78-043 TP-1 78-043 TP-1 78-043 TP-1 78-043 TP-1 78-043 TP-178-043 PCWO 843771 PCWO 843796 Page 1 of 2

EPU TEST 42 REQUIRED I&C SURVEILLANCES A

F F

,ttachment B

-P-199-009

evision 1

age 34 of 81 Work Item Instrument RBM 1A RBM 1B RBM 1A RBM 1B PSH-C72-1 N003A-D FIS-B21 -1 N008A&B and FIS-B21 -1 N009A&B Description RBM Channel 1A RBM Channel 1B RBM Channel A RBM Channel B Turbine First Stage Pressure Channels Main Steam Line Flow Channels Surveillance SI-178-255 SI-178-256 SI-178-345 SI-178-346 PCWO 779193 RTSV 833184 SI-183-207 SI-183-206 SI-183-205 SI-183-204 I

Confirmed By Date Page 2 of 2

Attachment C TP-1 99-009 Revision 1 Page 35 of 81 Test Condition A and MELLLA TC A Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 3

5.1 12B 42 10 5.2 4

100 22.1 22.2 100 100 Mode 5 Mode 5 Mode 5 Mode 5 Mode 5 or Mode 4 Mode 4 AND/OR

- 1580 MWt (40%)

Mode 2

-632 MWt (16%)

following gen sync

- Every 120 MWt (3%) following gen sync up to 60%

-1027 MWt (26%)

-1500 MWt (38%)

-1976 MWt (50%)

RE-081-036 TP-055-001 TP-199-009 Attachment L TP-199-009 Attachment B TP-1 99-009 Attachment T SR-1 55-004 SR-100-008 TP-1 62-030 TP-193-041 TP-193-041 TP-162-030 TP-162-030 Core Fuel Pool Verification CRD Stroke Time RBM Calibration I&C Surveillances IRM Surveillances Scram Time Measurements of Control Rods In Sequence Critical and Shutdown Margin Demo.

Steam Dryer Steady State Vibration Data Pressure Regulator Incremental Regulation Scram Bypass Setpoint Verification Steam Dryer Steady State Vibration Data Steam Dryer Steady State Vibration Data Page 1 of 2

Attachment C TP-199-009 Revision 1 Page 36 of 81 Test Condition A and MELLLA TC A Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 22.3 2371 MWt (60%)

TP-193-041 Pressure Regulator Step Changes and Pressure Regulator Failure ST 22.1

- Every 120 MWt TP-193-041 Pressure Regulator Incremental Regulation (3%) from 60% to 94.4%

100

-2569 MWt (65%)

TP-162-030 Steam Dryer Steady State Vibration Data (normal start of 3rd and Plant Walkdown RFP) 100 2873 MWt (72.7%)

TP-162-030 Steam Dryer Steady State Vibration Data 100 2873 MWt (72.7%)

TP-162-030 Steam Dryer Vibe Data with one MSIV Closed using TP-183-013 100 3039 MWt (76.9%)

TP-162-030 Steam Dryer Steady State Vibration Data 100 3039 MWt (76.9%)

TP-162-030 Steam Dryer Vibe Data with one MSIV Closed using TP-183-013 11 3039 MWt (72.7%)

SR-178-012 LPRM Calibration

+/- 7MWt 12A.2 3039 MWt (72.7%)

TP-199-009 APRM Calibration

+/- 7MWt After Attachment M LPRM Cal 19 72.7%

TP-199-009 Core Thermal Limits Attachment N 19 MELLLA TC A TP-199-009 Core Thermal Limits Attachment N 29.1 MELLLA TC A TP-164-036 Reactor Recirc Flow Control for MELLLA 10 TP-199-009 SRM/IRM Overlap Attachment T Page 2 of 2

Attachment D TP-199-009 Revision 1 Page 37 of 81 120 110 100 90 80 a) 0 E~

70 60 50 40 30 20 10 0

0 100 110 0

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

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

Attachment E TP-199-009 Revision 1 Page 38 of 81 Test Condition B Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 101 TP-100-013 Baseline Data Collection & Extrapolation 12A.2 TP-199-009 APRM Calibration Attachment M 19 TP-199-009 Core Thermal Limits Attachment N 22.1 Every 120 MWt TP-193-041 Pressure Regulator Incremental Regulation (3%)

223 TP-193-041 Pressure Regulator Step Changes 23 TP-045-001 Feedwater Level Setpoint Changes 24 TP-193-041 Turbine Valve Surveillance Page 1 of 1

Attachment F TP-199-009 Revision 1 Page 39 of 81 Test Condition C and MELLLA TC B Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 100 3293 MWt (83.3%)

TP-199-009 Steam Dryer Steady State Vibration Data Attachment Y, Step 1 100 3489 MWt (88.2%)

TP-199-009 Steam Dryer Steady State Vibration Data Attachment Y, Step 2 101 TP-100-013 Baseline Data Collection & Extrapolation 11 SR-178-012 LPRM Calibration 12A.2 3489 MWt (88.2%)

TP-199-009 APRM Calibration Attachment M 12B MELLLA TC B TP-199-009 RBM Calibration Attachment L 19 MELLLA TC B TP-199-009 Core Thermal Limits Attachment N 19 Prior to MELLLA TP-199-009 Core Thermal Limits TC B Attachment N 1A TP-199-009 Chemical and Radiochemical Attachment S 1B Prior to MELLA TP-199-009 Moisture Carryover TCB 100 Mlb/hr Attachment G 1 B MELLLA TC B TP-199-009 Moisture Carryover 82 Mlb/hr Core Attachment G Flow 3489 MWt (88.2%)

2 TP-1 99-009 Radiation Measurements Attachment U TP-193-041 Pressure Regulator Incremental Regulation 22.1 Page 1 of 2 Every 120 MWt

Attachment F TP-1 99-009 Revision 1 Page 40 of 81 Test Condition C and MELLLA TC B Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements (3%)

22.3 TP-193-041 Pressure Regulator Step Changes and Pressure Regulator Failure TP-045-001 Feedwater Level Setpoint Changes 23 24 29.1 32 35 Prior to MELLLA TC B MELLLA TC B 100 Mlb/Hr Prior to MELLLA TC B TP-193-041 TP-1 64-036 SO-100-107 TP-164-031 Turbine Valve Surveillance Reactor Recirc Flow Control for MELLLA Drywell Cooling (SO-100-107 Item 10)

Core Flow Calibration Page 2 of 2

Attachment G TP-1 99-009 Revision 1 Page 41 of 81 MOISTURE CARRYOVER SUPPORT DATA ST 1 B Moisture Carryover Testing Completion of the following steps satisfies the requirement of ST 1 B:

1.

Instruct Chemistry to perform CH-SY-026 "Moisture Carry Over."

2.

Attach copy of Core Performance Verification Printouts created during performance of ST-1 9 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 NFLO1 NFL02 NFL03 MSL Flow NFF01 NFF02 NFF03 NFF04 Total Feedwater flow FPA10 (Mlb/hr) 10 minute average CRD flow (Mlb/hr)

NEF52 Page 1 of 1

Attachment H TP-1 99-009 Revision 1 Page 42 of 81 Unit I Station Verification of Activities for ascending above 3489 MWt.

All action items required for power ascension above 3489 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

Attachment I TP-1 99-009 Revision 1 Page 43 of 81 Test Condition D Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results Summary All TERs Subtest Conditions Number Reviewed Dispositioned Number Requirements 100 Initial ascension to TP-199-009 Steam Dryer Vibe Monitoring During 3611 MWt (91.3%)

Attachment Z, Ascension Step 1 & 2 100 3611 MWt (91,3%)

TP-199-009 Steam Dryer Steady State Vibration Data Attachment Z Steps 3 through 6 101 TP-100-013 Baseline Data Collection & Extrapolation 12A.2 TP-199-009 APRM Calibration Attachment M 19 TP-199-009 Core Thermal Limits Attachment N 22.1

- Every 120 MWt TP-193-041 Pressure Regulator Incremental Regulation (3%)

22.3 TP-193-041 Pressure Regulator Step Changes 23 TP-045-001 Feedwater Level Setpoint Changes 24 Max Power TP-193-041 Turbine Valve Surveillance Acceptable 1B TP-199-009 Moisture Carryover Attachment G Page 1 of 1

Attachment J TP-199-009 Revision 1 Page 44 of 81 Unit 1 Station Verification of Activities for ascending above 3611 MWt.

All action items required for power ascension above 3611 MWt for which my group is responsible have been completed.

/

Manager - Nuclear Operations I

Manager - Nuclear Maintenance Supervisor - Reactor Engineering I

Supervisor - Health Physics I

Supervisor - Chemistry Manager - Nuclear Systems Engineering

/

Manager - Special Projects Page 1 of 1

Attachment K TP-199-009 Revision 1 Page 45 of 81 Test Condition E Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results All TERs Summary Subtest Conditions Number Reviewed Dispositioned Number Requirements 100 Initial ascension to TP-199-009 Steam Dryer Vibe Monitoring During 3733 MWt (94.4%)

Attachment AA, Ascension 100 100 100 100 100 101 103 11 12A.2 3733 MWt (94.4%)

100 Mlb/Hr Core Flow 3733 MWt (94.4%) 91 MIb/Hr Core Flow 100 to 108 MIb/Hr Core Flow 3733 MWt (94.4%)

108 MIb/Hr Core Flow 3733 MWt (94.4%)

Target Core Flow 3733 MWt (94.4%)

Step 1 TP-199-009 Attachment AA, Step 2 TP-199-009 Attachment AA, Step 3 TP-199-009 Attachment AA, Step 4 TP-199-009 Attachment AA, Step 5 TP-199-009 Attachment AA, Step 6 TP-144-048 SR-178-012 TP-199-009 Attachment M SE-178-001(2)(3)(4)

RE-OTP-201 Steam Dryer Steady State Vibration Data and Plant Walkdown Steam Dryer Steady State Vibration Data Steam Dryer Vibe Monitoring During Core Flow Sweep Steam Dryer Steady State Vibration Data Attachment AA, Step 5 Steam Dryer Steady State Vibration Data Baseline Data Collection & Extrapolation Condensate Pump Trip LPRM Calibration APRM Calibration APRM 1(2)(3)(4) Drive Flow Calibration TIP Uncertainty 12A.3 18 Page 1 of 2

Attachment K TP-199-009 Revision 1 Page 46 of 81 Test Condition E Review Summary TP-199-009 Additional Plant Procedure Description Test Completed Results All TERs Summary Subtest Conditions Number Reviewed Dispositioned Number Requirements 19 TP-199-009 Core Thermal Limits Attachment N IA TP-199-009 Chemical and Radiochemical Attachment S 1B 3733 MWt (94.4%)

TP-199-009 Moisture Carryover 108 Mlb/hr Core Attachment G Flow 1B 3733 MWt (94.4%)

TP-199-009 Moisture Carryover 91 MIb/hr Core Attachment G Flow 2

TP-199-009 Radiation Measurements Attachment U 22.1

~ Every 120 MWt TP-193-041 Pressure Regulator Incremental (3%)

Regulation 22.5 TP-193-041 SLRC Eval and Incremental Regulation Evaluation 29.2 S1-164-305 Recirc MG Set Positioners High Speed Stops 32 3733 MWt (94.4%)

SO-100-107 Drywell Cooling 108 MIb/Hr Core Item 10 Flow 35 3733 MWt (94.4%)

TP-164-031 Core Flow Calibration 100 MIb/Hr 36 TP-199-010 Cooling Water Systems 49 SI-179-360 MSL Rad Monitor adjustment Page 2 of 2

Attachment L TP-199-009 Revision 1 Page 47 of 81 ST 12B RBM TESTING Completion of the following steps satisfies the requirement for ST 12B and MELLLA ST 12B testing:

S1. Confirm that RBM instrument adjustments have been properly set for the observed RBM noise level. (Source - MELLLA Test 12B Test 2).

2. Confirm that RBM trip setpoints are properly set. (Source - MELLLA Test 12B Test 3).

3. Confirm that the RBM trips are enabled at the proper power levels. (Source -

MELLLA Test 12B Test 4).

__ 4. Level 1 Acceptance Criterion a, test 12B. Confirm that the RBM setpoints reflect the appropriate EPU settings.

__ 5. 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

Attachment M TP-199-009 Revision 1 Page 48 of 81 ST 12A APRM TESTING TEST CONDITION A Completion of the following steps satisfies the requirement for ST 12A and MELLLA ST 12A testing during Test Condition A:

1.

Confirm ST-il LPRM Calibration (SR-1 78-012) has been completed at current power level.

2. Perform SO-178-004.

___ 3.

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

__ 4. Level 1 Acceptance Criterion b, test 12A. Confirm that Technical Specifications on APRM scram and rod block setpoints are not being exceeded.

5. Confirm that the calibration of the APRMs to CLTP is consistent with Technical Specifications. (Source - MELLLA Test 12A Test 1)

__. 6. Confirm PRNMS drive flow signal gain has been adjusted such that flow signal is properly normalized. (Source - Test 12A Test 2).

__ 7. Confirm that the APRM flow-biased scram AND rod block setpoints correspond to MELLLA values (based on the ALs in EC-PUPC-1 0500 - ARTS/MELLLA TASK REPORT T0500 NEUTRON MONITORING SYSTEM). (Source - Test 12A Test 3).

8. Confirm that all APRM (fixed AND flow-biased) trip AND alarm functions have been validated. (Source - Test 12A Test 4).

Confirmed By Date Station Engineering Page 2 of 1

Attachment N TP-199-009 Revision 1 Page 49 of 81 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-100-007, Attachment A, Item 12.

__ 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-1 00-007 item 12.

3. Level 1 Acceptance Criterion b, test 19. Confirm that steady state reactor power is limited to the maximum value of the lesser of either 3733 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 Reactor Engineering.

Confirmed By Date Station Engineering Page 1 of 1 TP-1 99-009 Revision 1 Page 50 of 81 TEST PLATEAU REVIEW RECORD

1. Identify current Test Plateau:_________

2. List all tests scheduled for this current Test Plateau which were not completed to the extent required and the related Test Exception Reports.

3. List all tests completed during the current Test Plateau for which EPU Test Results Summaries have not been reviewed and the related Test Exception Reports.

4. List all Test Exception Reports which remain open.

SUMMARY

All testing scheduled for the current Test Plateau has been successfully completed to the extent required, including related analysis, and EPU Test Results Summaries have been reviewed with the exception of the open items listed above. All Test Exception Reports have been resolved. The open items list can be carried without impacting the safe operation of the plant.

Test Plateau Review completed and recommended for approval:

Date EPU Test Program Director TRO Meeting:-________I PORO Meeting:

________/____

Test Plateau Review Approved:

VP - Nuclear Operations Date Page 1 of 1

Attachment P TP-199-009 Revision 1 Page 51 of 81 ST 12A APRM TESTING NON-TEST CONDITION A Completion of the following steps satisfies the requirement for ST 12A and MELLLA ST 12A testing during Test Conditions other than Test Condition A:

1.

Confirm completion of SO-178-004.

__ 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

Attachment Q TP-199-009 Revision 1 Page 52 of 81 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.

3. List all tests completed during the DPU Test Program for which EPU Test Results Summaries have not been reviewed and the related Test Exception Reports.

4. List all Test Exception Reports which remain open.

SUMMARY

All testing scheduled for the EPU Test Program has been successfully completed to the extent required, including related analysis, and EPU Test Results Summaries have been reviewed with the exception of the open items listed above. All Test Exception Reports have been resolved. The open items list can be carried without impacting the safe operation of the plant.

Test Plateau Review completed and recommended for approval:

/

Date EPU Test Program Director TRC Meeting:

/

PORC Meeting:

/

Test Plateau Review Approved:

VP - Nuclear Operations Date I

Page 1 of 1

Attachment R TP-199-009 Revision 1 Page 53 of 81 TP-199-009 SUBTEST NUMBERS M--1563 or MELLLA Number TP-199-009 Subtest Number Description or Title Implementing Procedure Number 1

1A 1

1B 2

2 3

3 4

4 5

5.1 5

5.2 10 10 11 11 12 12A.1 12 12A.2 12 12A.3 12 12A.4 12 12A.5 12 12A.6 12 12B 18 18 19 19 Chemical and Radiochemical Moisture Carryover Radiological Survey Program in Support of the Unit 1 EPU Modification Core Fuel Pool Verification In Sequence Critical and Shutdown Margin Demo.

CRD Stroke Time Scram Time Measurements of Control Rods SRM/IRM Overlap (GO-100-002 Item 5.31)

LPRM Calibration Validation of Core Thermal Power Heat Balance APRM Calibration APRM 1 Drive Flow Calibration APRM 2 Drive Flow Calibration APRM 3 Drive Flow Calibration APRM 4 Drive Flow Calibration RBM Calibration TIP Uncertainty Core Thermal Limits TP-199-009 Attachment S TP-1 99-009 Attachment G HP-TP-521 RE-081-036 SR-100-008 TP-055-006 SR-155-004 GO-100-002 SR-178-012 RE-1TP-026 TP-199-009 Attachment M SE-178-001 SE-178-002 SE-1 78-003 SE-1 78-004 TP-199-009 Attachment L RE-OTP-201 TP-199-009 Attachment N Page 1 of 3

Attachment R TP-1 99-009 Revision 1 Page 54 of 81 Implementing Description or Procedure Title Number M-1563 or MELLLA Number TP-199-009 Subtest Number 22 22 22 22 23 24 29 29 32 33 35 36 36 36 37 22.1 22.2 22.3 22.4 23 24 29.1 29.2 32 33.1 35 36.1 36.2 36.3 37 Pressure Regulator Incremental Regulation Scram Bypass Setpoint Verification Pressure Regulator Step Changes and Ctrl Failures SLRC Eval and Incremental Regulation Evaluation Feedwater Level Setpoint Changes Turbine Valve Surveillance Reactor Recirc Flow Control for MELLLA Recirc MG Set Positioners High Speed Stops Drywell Cooling Recirc and MSL Steady State Vibration Core Flow Calibration Cooling Water Systems Cooling Water Systems Cooling Water Systems Gaseous Radwaste Systems (Combined with ST 1A)

I&C Surveillances MSL Rad Monitor Adjustment Steam Dryer Steady State Vibration Data Steam Dryer Vibe Data During MSIV Closure Steam Dryer Vibe Monitoring During Ascension Plant Walkdown TP-1 93-041 TP-1 93-041 TP-193-041 TP-193-041 TP-045-001 TP-1 93-041 TP-1 64-036 SI-164-305 SO-1 00-107 Item 10 TP-183-012 TP-164-031 TP-111-004 TP-114-011 TP-1 15-010 TP-1 99-009 Attachment S TP-199-009 Attachment B SI-179-360 TP-162-030 TP-162-030 TP-1 62-030 TP-162-030 42 42 49 100 100 100 100 49 100.1 100.2 100.3 100.4 Page 2 of 3

Attachment R TP-199-009 Revision 1 Page 55 of 81 M-1563 or MELLLA Number TP-199-009 Subtest Number Description or Title Implementing Procedure Number 101 103 101 103 Baseline Data Collection & Extrapolation TP-100-013 TP-144-048 Condensate Pump Trip Page 3 of 3

Attachment S TP-199-009 Revision 1 Page 56 of 81 ST-1A CHEMICAL AND RADIOCHEMICAL (Includes ST 37 Gaseous Radwaste)

Enter Test Condition Completion of the following steps satisfies the requirements for ST 1 A and 37.

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

a.

b.

c.

d.

e.

f.

__ 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

Attachment T TP-199-009 Revision 1 Page 57 of 81 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-1 78-301A is current (NIMS Activity #Z0304-01).

__ 2.

Confirm that 184DAY IRM CALIB CHANNEL B SI-178-301B is current (NIMS Activity #Z0394-01).

__ 3.

Confirm that 184DAY IRM CALIB CHANNEL C SI-178-301C is current (NIMS Activity #Z0393-01).

__ 4.

Confirm that 184DAY IRM CALIB CHANNEL D SI-1 78-301D is current (NIMS Activity #Z0392-01).

5.

Confirm that 184DAY IRM CALIB CHANNEL E SI-178-301E is current (NIMS Activity #Z0391 -01 ).

6.

Confirm that 184DAY IRM CALIB CHANNEL F SI-178-301F is current (NIMS Activity #Z0390-01).

7.

Confirm that 184DAY IRM CALIB CHANNEL G SI-178-301G is current (NIMS Activity #Z0389-01).

8.

Confirm that 184DAY IRM CALIB CHANNEL H SI-1 78-301H is current (NIMS Activity #Z0388-01)

Confirmed By Date Test Condition A Testing: Confirm that the SRM/IRM Overlap has been successfully demonstrated as documented in GO-1 00-002 Item 5.31, OR Prepare a Test Exception Report documenting that the SRM/IRM Overlap has not been demonstrated in Test Condition A.

Overlap has been successfully demonstrated in Test Condition A.

Test Exception Report has been written.

Confirmed By Date Page 1 of 1

Attachment U TP-1 99-009 Revision 1 Page 58 of 81 ST-2 RADIATION MEASUREMENTS Enter Test Condition Completion of the following steps satisfies the requirements for ST 2.

1. Confirm completion of HP-TP-521.

2. Confirm that the following Level 1 Acceptance Criterion is satisfied: The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of The Standard for Protection Against Radiation as outlined in 1 OCFR20.

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) 1 0.5 mRem/hr II 2.5 mRem/hr III 15 mRem/hr IV 100 mRem/hr Note: All areas designated Radiation Zone V have potential radiation doses of 100 mRem/hr. Readings taken in Zone V during the EPU Test Program may be less than 100 mRem/hr; however, since Zone V is defined in terms of potential levels, there are no Acceptance Criteria for Zone V survey points.

Verified By Date Page 1 of 1

Attachment V TP-199-009 Revision 1 Page 59 of 81 ST-22 PRESSURE REGULATOR Enter Test Condition ______

In Test Condition A, Record power levels at which the RSCS an d RWM scram bypasses cleared, and confirm that both cleared before exceeding 26% power. N/A this section for Test Conditions B through E.

RSCS RWM_____

____/

Confirmed By Date In Test Conditions A through D, Perform the following steps. N/A this section for Test Condition E.

1_

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

__2.

Confirm actual Control Valve position is within +1 % to -3% of predicted values as required by Level 2 Acceptance Criterion.

__3.

Confirm all observed decay ratios were less than 1.0 as required by Level 1 Acceptance Criterion.

__4.

Confirm all observed decay ratios were less or equal to 0.5 as required by Level 2 Acceptance Criterion.

__5.

Confirm all pressure response times were less than or equal to 10 seconds as required by Level 2 Acceptance Criterion.

__6.

Confirm all steam flow steady state limit cycles produced steam flow variations no larger than +/-0.5% as required by Level 2 Acceptance Criterion.

__7.

Confirm peak neutron flux remained below scram setting by at least 7.5% as required by Level 2 Acceptance Criterion.

__8.

Confirm peak vessel pressure remained below scram setting by at least 10 psi as required by Level 2 Acceptance Criterion.

Confirmed By Date Page 1 of 2

Attachment V TP-1 99-009 Revision 1 Page 60 of 81 In Test Condition E, Perform the following steps. N/A this section for Test Conditions A through D.

1_

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 3rd 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

Attachment W TP-1 99-009 Revision 1 Page 61 of 81 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 0 of 11

Attachment X TP-199-009 Revision 1 Page 62 of 81 Initial Power Ascension to 77% Power Ol

1.

DURING approach to Initial Criticality, perform ST-4, In Sequence Critical and Shutdown Margin Demonstration.

O

2.

AFTER the main generator has been synchronized to the grid AND stable conditions have been established, O

2.1 Maintain reactor power within a tolerance of +/- 3 MWt as displayed on PICSY point NBA101 during data collection.

O 2.2 Record reactor operating conditions at the time the dryer data is recorded.

O 2.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

O 2.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

3.

Inform Operations that the tolerance of +/- 3 MWt on reactor power is no longer in effect.

I NOTE:

A "Full Limit Evaluation" means going through the exercise of processing the strain gauge and A4 measurements and comparing the results against the Level 1/Level 2 acceptance criteria, determining that there is sufficient margin to go up the next step in power, and comparing the strain gauge, accelerometer, MSL and pressure transducer frequency spectra against their "reference guidance" curves.

0J

4.

Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

I Confirmed By EPU Date 0i

5.

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

/

I Confirmed By EPU Date 0

6.

Commence collection of Pressure Regulator Incremental Regulation data per ST-22.

This data should be collected at intervals not to exceed 3% (of scale) reactor power.

Page 1 of 11

Attachment X TP-1 99-009 Revision 1 Page 63 of 81 O

7.

Inform Operations that vibration test results are acceptable and that reactor power level may be increased to 38%.

1 NOTE:

Step 9 may be performed before, during or after Step 8 O

8.

Perform ST-22 Scram Bypass Setpoint Verification during power ascension.

O

9.

Evaluate Steam Dryer Instrumentation dataset and Determine if sufficient margin is available to accommodate power ascension to 72.7% reactor power without evaluating the measurements against the acceptance criteria at each intermediate test point.

Record results of evaluation below:

[]

YES, sufficient margin is available to accommodate power ascension to 72.7%

reactor power without evaluating the measurements against the acceptance criteria at each intermediate test point.

El

-NO, sufficient margin does not exist. A Full Limit Evaluation of measurements against the acceptance criteria at each intermediate test point is required.

Confirmed By Date NOTE:

ST-5 CRD Scram Timing may be performed prior to or after the next 2 steps but not during the next 2 steps O

10.

AFTER achieving 38% reactor power, o

10.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101 during data collection.

St10.2 Record reactor operating conditions at the time the dryer data is recorded.

O 10.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

EO 10.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

11.

Inform Operations that the tolerance of +/- 7 MWt on reactor power is no longer in effect.

Page 2 of 11

Attachment X TP-1 99-009 Revision 1 Page 64 of 81 O

12.

IF the recorded answer in step 9 is YES, THEN N/A this step and proceed to the next step; ELSE Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O

13.

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

Confirmed By Date EPU O

14.

Inform Operations that vibration test results are acceptable and that reactor power level may be increased to 50%.

O

15.

AFTER achieving 50% reactor power, O]

15.1 Maintain reactor power within a tolerance of +/- 10 MWt as displayed on PICSY point NBA101 during data collection.

O 15.2 Record reactor operating conditions at the time the dryer data is recorded.

O 15.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

jJ 15.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

o

16.

Inform Operations that the tolerance of +/- 10 MWt on reactor power is no longer in effect.

O

17.

IF the recorded answer in step 9 is YES, THEN N/A this step and proceed to the next step; ELSE Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU Page.3 of 11

Attachment X TP-199-009 Revision 1 Page 65 of 81 O

18.

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

Confirmed By Date EPU O

19.

Inform Operations that vibration test results are acceptable and that reactor power level may be increased to 60%.

IJ

20.

Complete TP-199-009 Attachment V to satisfy requirements for ST-22.1 performance up to and including 60% power.

O

21.

Perform ST-22.3, Pressure Regulator Step Changes and Pressure Regulator Failure.

o

22.

Continue collection of Pressure Regulator Incremental Regulation data per ST-22. This data should be collected at intervals not to exceed 3% (of scale) reactor power.

O

23.

Increase reactor power to 65%.

NOTE:

Step 24 may be performed at any time in parallel with steps 25 through 27 or postponed until after step 27.

O

24.

Perform the following in any order or combination:

O 24.1 Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation in accordance with TP-162-030 O]

24.2 Perform Walkdown of accessible areas in accordance with TP-162-030 O]

24.3 Perform Remote Walkdown of inaccessible areas in accordance with TP-1 62-030 O

25.

Maintain reactor power within a tolerance of +/- 12 MWt as displayed on PICSY point NBA101 during the following steps that may be performed in any order or combination:

O 25.1 Record reactor operating conditions at the time the dryer data is recorded.

o]

25.2 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

Ol 25.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O 25.4 Record a dataset of MSL, FW, Recirculation, RHR and Extraction Steam accelerometers in accordance with TP-1 62-030 Page 4 of 11

Attachment X TP-199-009 Revision 1 Page 66 of 81 O

25.5 Record a dataset of Recirculation and RHR Strain Gauges in accordance with TP-162-030 o

26.

Inform Operations that the tolerance of +/- 12 MWt on reactor power is no longer in effect.

O]

27.

IF the recorded answer in step 9 is YES, THEN N/A this step and proceed to the next step; ELSE Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O

28.

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

Confirmed By Date EPU O

29.

Inform Operations that vibration test results are acceptable and that reactor power level may be increased to 72.7%

NOTE:

ST-1 1, ST-1 2A.2 and ST-1 9, LPRM and APRM Calibrations and Core Thermal Limits, may be performed prior to, after or in parallel with steps 30 through 34.

O

30.

AFTER achieving 72.7% reactor power, o1 30.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBAI01 during data collection.

Ol 30.2 Record reactor operating conditions at the time the dryer data is recorded.

O 30.3 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

O 30.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O]

31.

Inform Operations that the tolerance of +/- 7 MWt on reactor power is no longer in effect.

Page 5 of 11

Attachment X TP-1 99-009 Revision 1 Page 67 of 81 o

32.

Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU o

33.

Evaluate Steam Dryer Instrumentation datasets and Determine if sufficient margin is available to accommodate the expected pressure load increase resulting from the MSIV closure tests. Record results of evaluation below:

O

__YES, sufficient margin is available to accommodate the expected pressure load increase resulting from the MSIV closure tests.

o

-NO, sufficient margin does not exist. DO NOT perform MSIV closure vibration testing. N/A steps 34 through 48 and prepare a Test Exception Report documenting the failure to perform these tests.

Confirmed By Date O

34.

Confirm that proper core conditions have been established for MSIV closure vibration testing.

Confirmed By Date Reactor Engineering O

35.

Simulate steam flow conditions that will exist at 94.4% power by Closing MSIVs in MSL A in accordance with TP-1 83-013.

0

36.

Perform the following steps in parallel:

O]

36.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

0 36.2 Record reactor operating conditions at the time the dryer data is recorded.

O1 36.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

O 36.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

0

37.

Restore normal steam flow conditions by Opening MSIVs in MSL A in accordance with TP-183-013.

Page 6 of 11

Attachment X TP-1 99-009 Revision 1 Page 68 of 81 jJ

38.

Simulate steam flow conditions that will exist at 94.4% power by Closing MSIVs in MSL B in accordance with TP-183-013 O

39.

Perform the following steps in parallel:

O 39.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA1 01.

O 39.2 Perform a walkdown of HPCI steam piping in accordance with TP-1 62-030.

5 39.3 Record reactor operating conditions at the time the dryer data is recorded.

O 39.4 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

O 39.5 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

40.

Restore normal steam flow conditions by Opening MSIVs in MSL B in accordance with TP-1 83-013.

0

41.

Simulate steam flow conditions that will exist at 94.4% power by Closing MSIVs in MSL C in accordance with TP-1 83-013.

o

42.

Perform the following steps in parallel o

42.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

O 42.2 Record reactor operating conditions at the time the dryer data is recorded.

O 42.3 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

5 42.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

43.

Restore normal steam flow conditions by Opening MSIVs in MSL C in accordance with TP-183-013.

O]

44.

Simulate steam flow conditions that will exist at 94.4% power by Closing MSIVs in MSL D in accordance with TP-1 83-013.

Page 7 of 11

Attachment X TP-199-009 Revision 1 Page 69 of 81 O

45.

Perform the following steps in parallel:

El 45.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA1 01.

O 45.2 Record reactor operating conditions at the time the dryer data is recorded.

O 45.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

El 45.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

46.

Restore normal steam flow conditions by Opening MSIVs in MSL D in accordance with TP-183-013.

0

47.

Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation datasets AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O

48.

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

Confirmed By Date EPU IJ

49.

Inform Operations that vibration test results are acceptable and that reactor power level may be increased to 76.9%.

5

50.

AFTER achieving 76.9% reactor power, O

50.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101 during data collection.

O 50.2 Record reactor operating conditions at the time the dryer data is recorded.

O 50.3 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

O 50.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

Page 8 of 11

Attachment X TP-199-009 Revision 1 Page 70 of 81 o

51.

Inform Operations that the tolerance of +/- 7 MWt on reactor power is no longer in effect.

o

52.

Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria Confirmed By Date O

53.

Evaluate Steam Dryer Instrumentation datasets and Determine if sufficient margin is available to accommodate the expected pressure load increase resulting from the MSIV closure tests. Record results of evaluation below:

O

_YES, sufficient margin is available to accommodate the expected pressure load increase resulting from the MSIV closure tests.

O

___ NO, sufficient margin does not exist. DO NOT perform MSIV closure vibration testing. N/A steps 54 through 67 and prepare a Test Exception Report documenting the failure to perform these tests.

Confirmed By Date O

54.

Confirm that proper core conditions have been established for MSIV closure vibration testing.

Confirmed By Date Reactor Engineering O

55.

Simulate steam flow conditions that will exist at 100% power by Closing MSIVs in MSL A in accordance with TP-183-013.

O

56.

Perform the following steps in parallel:

O 56.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

O 56.2 Record reactor operating conditions at the time the dryer data is recorded.

O 56.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

O 56.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

Page 9 of 11

Attachment X TP-199-009 Revision 1 Page 71 of 81 O

57.

Restore normal steam flow conditions by Opening MSIVs in MSL A in accordance with TP-183-013.

O

58.

Simulate steam flow conditions that will exist at 100% power by Closing MSIVs in MSL B in accordance with TP-1 83-013.

O

59.

Perform the following steps in parallel:

O]

59.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

O 59.2 Perform a walkdown of HPCI steam piping in accordance with TP-162-030.

o 59.3 Record reactor operating conditions at the time the dryer data is recorded.

O 59.4 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

O 59.5 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

60.

Restore normal steam flow conditions by Opening MSIVs in MSL B in accordance with TP-1 83-013.

O

61.

Simulate steam flow conditions that will exist at 100% power by Closing MSIVs in MSL C in accordance with TP-1 83-013.

O

62.

Perform the following steps in parallel:

EO 62.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

O 62.2 Record reactor operating conditions at the time the dryer data is recorded.

O 62.3 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

0 62.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

Q

63.

Restore normal steam flow conditions by Opening MSIVs in MSL C in accordance with TP-183-013.

0

64.

Simulate steam flow conditions that will exist at 100% power by Closing MSIVs in MSL D in accordance with TP-183-013.

Page 10 of 11

Attachment X TP-199-009 Revision 1 Page 72 of 81 E]

65.

Perform the following steps in parallel:

O]

65.1 Maintain reactor power within a tolerance of +/- 7 MWt as displayed on PICSY point NBA101.

EO 65.2 Record reactor operating conditions at the time the dryer data is recorded.

O 65.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

O 65.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O

66.

Restore normal steam flow conditions by Opening MSIVs in MSL D in accordance with TP-1 83-013.

EJ

67.

Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation datasets AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU Q

68.

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

Confirmed By Date EPU Page 11 of 11

Attachment Y TP-199-009 Revision 1 Page 73 of 81 INITIAL POWER ASCENSION TO 88% POWER EJ

1.

ST-100 Vibration Testing During Ascent to Test Condition C 5]

1.1 Inform Shift Supervision to Establish AND Maintain reactor power between 3825 MWt and 3301 MWt (83.3% +/-0.25%)

5 1.2 Record reactor operating conditions at the time the dryer data is recorded.

O 1.3 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

O]

1.4 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O 1.5 Inform shift Supervision to Establish reactor conditions within those defined as EPU Test Condition C in Attachment D.

O]

2.

ST-100 Vibration Testing At 3489 MWt O

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

NOTE:

Steps 2.2 and 2.3 may be performed in parallel.

5 2.2 Perform the following in any order or combination:

O 2.2.1 Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation in accordance with TP-162-030 El 2.2.2 Perform Walkdown of accessible areas in accordance with TP-162-030 E5 2.2.3 Perform Remote Walkdown of inaccessible areas in accordance with TP-162-030 5

2.2.4 Record a dataset of MSL, FW, Recirculation, RHR and Extraction Steam accelerometers in accordance with TP-1 62-030 5

2.2.5 Record a dataset of Recirculation and RR Strain Gauges in accordance with TP-1 62-030 E5 2.3 Perform the following steps in any order or combination:

5 2.3.1 Record reactor operating conditions at the time the dryer data is recorded.

Page 1 of 2

Attachment Y TP-1 99-009 Revision 1 Page 74 of 81 OJ 2.3.2 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

O 2.3.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O 2.4 AFTER completion of step 2.3, Inform Operations that the minimum power level of 3472 MWt is no longer in effect.

Page 2 of 2

Attachment Z TP-199-009 Revision 1 Page 75 of 81 INITIAL POWER ASCENSION TO 91% POWER AND TC-D STEADY STATE VIBRATION TESTING 0

1.

Inform personnel performing the following activities that we are about to commence the initial power ascension from 3489 MWt (88.2%) to 3611 MWt (91.3%) AND Confirm that all personnel are prepared to perform assigned activities.

0l 1.1 Steam Dryer Instrumentation recording in accordance with TP-1 62-030 0

1.2 Balance of Plant Vibration Instrumentation recording in accordance with TP-162-030.

0 1.3 RPV Steam Dryer Structural Integrity Monitoring in accordance with OI-TA-008.

0 1.4 Plant walkdown by Operations personnel.

0 1,5 Plant walkdown by Station Engineering personnel Confirmed By Date El

2.

Inform personnel performing the above activities that the initial power ascension from 3489 MWt (88.2%) to 3611 MWt (91.3%) has been completed.

El

3.

Steady State data collection at 3611 MWt 0l 3.1 Inform Shift Supervision to Maintain reactor power between 3593 MWt and 3611 MWt as displayed on PICSY point NBA101 during data collection.

NOTE:

Steps 3.2 and 3.3 may be performed in parallel.

Q 3.2 Perform the following in any order or combination:

El 3.2.1 Record a dataset of vibrations as required to be taken with Local Vibration Instrumentation in accordance with TP-162-030 El 3.2.2 Perform Walkdown of accessible areas in accordance with TP-1 62-030 El 3.2.3 Perform Remote Walkdown of inaccessible areas in accordance with TP-162-030 Ol 3.2.4 Record a dataset of MSL, FW, Recirculation, RHR and Extraction Steam accelerometers in accordance with TP-162-030.

El 3.2.5 Record a dataset of Recirculation and RHR Strain Gauges in accordance with TP-1 62-030.

Page 1 of 2

Attachment Z TP-199-009 Revision 1 Page 76 of 81 O

3.3 Perform the following steps in any order or combination:

O 3.3.1 Record reactor operating conditions at the time the dryer data is recorded.

EO 3.3.2 Record three 5 minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

ol 3.3.3 AFTER the dataset is recorded, evaluate the measeured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

o 3.4 AFTER completion of step 3.3, 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 3.5 Perform a full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O

4.

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

Confirmed By Date EPU O]

5. Prepare a steam dryer performance evaluation for 3611 MWt as required by License Condition 2.C.(36)(a)3.

Ol

6. Record date and time that information was provided to the NRC Project Manager.

Date Time Confirmed By Date Page 2 of 2

Attachment AA TP-1 99-009 Revision 1 Page 77 of 81 INITIAL POWER ASCENSION TO 94% POWER AND TC E VIBRATION TESTING

]

1.

Initial power ascension from 3611 MWt to 3733 MWt

]

1.1 Inform personnel performing the following activities that we are about to commence the initial power ascension from 3611 MWt (91.2%) to 3733 MWt (94.4%) AND Confirm that all personnel are prepared to perform assigned activities.

O]

1.1.1 Steam Dryer Instrumentation monitoring, recording and analysis in accordance with TP-162-030.

O 1.1.2 Balance of Plant Vibration Instrumentation monitoring, recording and analysis in accordance with TP-162-030.

O1 1.1.3 RPV Steam Dryer Structural Integrity Monitoring in accordance with' OI-TA-008.

Eo 1.1.4 Plant walkdown by Operations personnel E5 1.1.5 Plant walkdown by Station Engineering personnel Confirmed By Date 5]

1.2 Inform Operations that test personnel are prepared to collect data and that power ascension may begin.

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 1.3 AFTER 3733 MWt has been achieved, Inform personnel performing the above activities that the initial power ascension from 3611 MWt (91.3%) to 3733 MWt (94.4%) has been completed.

O

2.

Steady State Data Collection at 3733 MWt 100 MIb/Hr Core Flow O

2.1 Inform shift Supervision to Maintain reactor power between 3715 MWt and 3733 MWt as displayed on PICSY point NBA1 01, AND core flow between 99.5 MIb/Hr and 100.5 Mlb/Hr during data collection.

Page 1 of 5

Attachment AA TP-199-009 Revision 1 Page 78. of 81 NOTE:

Steps 2.2 and 2.3 may be performed in parallel.

I O

2.2 Perform the following in any order or combination:

O 2.2.1 Record a dataset of local instrumentation in accordance with TP-162-030 0

2.2.2 Perform Walkdown of accessible areas in accordance with TP-1 62-030 O

2.2.3 Perform Remote Walkdown of inaccessible areas in accordance with TP-162-030 O

2.2.4 Record a dataset of MSL, FW, Recirculation, RHR and Extraction Steam accelerometers in accordance with TP-1 62-030 O

2.2.5 Record a dataset of Recirculation and RHR Strain Gauges in accordance with TP-1 62-030 O

2.3 Perform the following steps in any order or combination:

El 2.3.1 Record reactor operating conditions at the time the dryer data is recorded.

O 2.3.2 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

Ol 2.3.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

2.4 AFTER completion of step 2.3, Inform Operations that the minimum power level of 3715 MWt and the restriction on core flow are no longer in effect.

E0 2.5 Perform a Full Limit Evaluation of the recorded Steam Dryer Instrumentation dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date EPU O

2,6 Prepare a steam dryer performance evaluation for 3733 MWt as required by License Condition 2.C.(36)(a)3.

Page 2 of 5

Attachment AA TP-1 99-009 Revision 1 Page 79 of 81 U

2.7 Record date and time that information was provided to the NRC Project Manager.

Date Time Confirmed By Date U

3.

Steady State data collection at 3733 MWt 91 MIb/Hr Core Flow 3.1 Inform Shift Supervision to Maintain reactor power between 3715 MWt and 3733 MWt as displayed on PICSY point NBA1 01, AND core flow between 91.5 MIb/Hr during data collection.

NOTE:

Steps 3.2 and 3.3 may be performed in parallel.

U 3.2 Perform the following steps in any order or combination:

U 3.2.1 Record reactor operating conditions at the time the dryer data is recorded.

3.2.2 Record one 5-minute segment dataset of Steam Dryer Instrumentation.

synchronized with MSL Strain Gauges in accordance with TP-162-030.

U 3.2.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

U 3.3 Perform ST-1 B Moisture Carryover.

U 3.4 AFTER completion of steps 3.2 and 3.3, Inform Operations that the minimum power level of 3715 MWt and the restriction on core flow are no longer in effect.

U

4.

Determination of Target Core Flow U

4.1 Confirm that Reactor Engineering has established a rod line that will enable Core Flow to be increased from approximately 100 MIb/Hr to 108 MIb/Hr with minimum adjustments required to control rods.

Confirmed By Date Reactor Engineering

[]

4.2 Confirm that personnel are available to record the following data:

El 4.2.1 Steam Dryer accelerations Page 3 of 5

Attachment AA TP-199-009 Revision 1 Page 80 of 81 O

4.2.2 Main Steam Line, Recirculation and Feedwater accelerations O]

4.2.3 Recirculation strain gauges Confirmed By Date Q

4.3 Record starting Core Mlb/Hr O

4.4 Record initial datasets.

O 4.5 Inform Operations to increase core Flow by 1 Mlb/Hr o

4.6 Record dataset.

O 4.7 Repeat steps 4.5 and 4.6 until Core Flow is established at 104 Mlb/Hr.

O 4.8 Inform Operations to increase Core Flow by 0.5 Mlb/Hr EO 4.9 Record dataset fJ 4.10 Repeat steps 4.8 and 4.9 until Core Flow is established at 108 Mlb/Hr.

O 4.11 Determine the core flow at which the dryer accelerations reached maximum amplitude during this step. This is the Target Core Flow.

Target Core flow Mlb/Hr Confirmed By Date O3

5.

Steady State data collection at 3733 MWt 108 Mlb/Hr Core Flow O

5.1 Inform Shift supervision to Maintain reactor power between 3715 MWt and 3733 MWt as displayed on PICSY point NBA1 01, AND core flow between 107 Mlb/Hr and 108 Mlb/Hr during data collection.

NOTE:

Steps 5.2 and 5.3 may be performed in parallel.

O3 5.2 Perform the following steps in any order or combination:

O 5.2.1 Record reactor operating conditions at the time the dryer data is recorded.

Page 4 of 5

Attachment AA TP-199-009 Revision 1 Page 81 of 81 O

5.2.2 Record one 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-1 62-030.

Ol 5.2.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

O 5.3 Perform ST-1 B Moisture Carryover Ol 5.4 AFTER completion of steps 5.2 and 5.3, Inform Operations that the minimum power level of 3715 MWt and the restriction on core flow are no longer in effect.

El

6.

Steady State data collection at 3733 MWt with Target Core Flow O

6.1 Record Target Core Flow from step 4:

MIb/Hr El 6.2 Inform Shift supervision to Maintain reactor power between 3715 MWt and 3733 MWt as displayed on PICSY point NBA1 01, AND core flow between +/- 0.5 MIb/Hr of the Target Core Flow during data collection.

5 6.3 Perform the following steps in any order or combination:

5 6.3.1 Record reactor operating conditions at the time the dryer data is recorded.

El 6.3.2 Record three 5-minute segment dataset of Steam Dryer Instrumentation synchronized with MSL Strain Gauges in accordance with TP-162-030.

El 6.3.3 AFTER the dataset is recorded, evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

El 6.4 AFTER completion of step 6.3, Inform Operations that the minimum power level of 2715 MWt and the restriction on core flow are no longer in effect.

Page 5 of 5

For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LL

C. PROCEDURE

STEAM DRYER AND FLOW INDUCED.VIBRATION TESTING TP-162-030 Revision 0 Page 1 of 25 ADHERENCE LEVEL: STEP-BY-STEP:

QUALITY CLASSIFICATION:

APPROVAL CLASSIFICATION:

( ) QA Program (X)

Non-QA Program (X)

Plant

( ) Non-Plant Instruction EFFECTIVE DATE:0e 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-162-030 Revision 0 Page 2 of 25 TABLE OF CONTENTS SECTION PAGE

1.

PURPOSE 4

2.

DISCUSSION 4

3.

REFERENCES 5

4.

TEST EQUIPMENT 6

5.

PRECAUTIONS 6

6.

PREREQUISITES 6

7.

PROCEDURE 7

7.1 Steam Dryer Instrumentation/Data Acquisition/Analysis 7

7.2 MSL Strain Gages (SGs) 8 7.3 MSL Accelerometer Data Acquisition/Analysis (Line B & C) 9 7.4 Feedwater Loop A Accelerometer Data Acquisition/Analysis 9

7.5 Recirculation/RHR Strain Gage Data Acquisition 10 7.6 Recirculation Loop A & B Accelerometer Data Acquisition/Analysis 10 7.7 RHR Valve HV151F015A(B) and HV151F017A(B) Accelerometer Data Acquisition/Analysis 11 7.8 Extraction Steam Accelerometer Data Acquisition/Analysis 11 7.9 Locally Monitored Acceleration Data Acquisition 12 7.10 Accessible Area Walkdowns 13 7.11 In-Accessible Area Walkdown 13 7.12 Pi Data Sheet Acquisition 14 7.13 OI-TA-008 Data Acquisition 14

8.

RESTORATION 15

For Information Only TP-1 62-030 Revision 0 Page 3 of 25 9.

10.

11.

ACCEPTANCE CRITERIA REVIEW RECORDS

!V-15 17 17 ATTACHMENTS ATTACHMENT A

B C

D E

Required Testing Data Collection/Analysis Support Guidelines to Evaluate Data Set(s) for Accelerometers Located Inside the Drywell Guidelines to Evaluate Data Set(s) for Accelerometers Located Outside the Drywell Guidelines for Evaluation of Data Set(s) for RHR HV151 F015A(B)

& HV1 51 FO 7A(B) Accelerometers Pi Steam Dryer Data Log Sheet (Info Only)

PAGE 18 19 20 22 24 F

25

For Information Only TP-1 62-030 Revision 0 Page 4 of 25

1.

PURPOSE This TP collects and analyzes vibration and 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 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 steam dryer Main Steam 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 in future engineering evaluations to predict the Unit 2 non-instrumented steam dryer performance.

2.

DISCUSSION Extended Power Uprate (EPU) is increasing the overall output of the Unit 1 Reactor by approximately 14% power. This increase in power output will be accomplished in 2 phases. The 151 phase will be a 7% increase in power. A new Rx vessel steam dryer has been installed to accommodate the increased steam flows and resultant increases in dryer loading. The Unit 1 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 1 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, pressure sensors, installed plant instrumentation and visual inspections will be employed to ensure the Unit 1 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-1 99-009 and TP-1 83-013 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.

For Information Only TP-1 62-030 Revision 0 Page 5 of 25 Phase 2 power levels, in excess of the 7% increase, are not covered by this TP. A new TP will be issued to address data collpction and analysis for power levels in excess of the 7% increase in Reactor power. Phase 2 will be accomplished in Unit 1, RFO# 16.

Data collected during implementation of this TP will also be used to benchmark the Main Steam Line (MSL) Limit Curves that will be used to analyze Unit 2 Rx vessel steam dryer. The MSL Limit Curves will also be used for Phase 2 of Unit 1 EPU. 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-2069, Rev 0, EPU Flow Induced Vibration Testing and Walkdown Criteria 3.2 TP&P No. 0000-0080-3146-01, Rev 0, Steam Dryer Vibration and Dynamic Pressure measurement During Power Ascension Test Plan & Procedure 3.3 GE-NE-0000-0080-2994-P-R4 Susquehanna Replacement Steam Dryer Instrumentation Acceptance Criteria - Dryer Mounted Instrumentation 3.4 GE-NE-0000-0080-8732-P-R1, Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation.

3.5 GE-NE-0000-0080-9157-P-RO, Susquehanna Replacement Steam Dryer - Dryer Mounted Pressure Transmitter Reference Curves 3.6 GE-NE-26A7374, Rev 0, Dryer Vibration Measurement Test Specification 3.7 TP-199-009, EPU Master Test Procedure Special, Infrequent or Complex Test/Evolution (SIC/TE) 3.8 TP-1 83-013, Setting Plant Conditions for MSL Vibration Data Collection for EPU 3.9

' 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-3310)," dated January 12, 2008.

3.10 EC 829123, Steam Dryer Instrumentation 3.11 EC 674923, EPU-Steam Dryer Upgrade-Unit 1 3.12 EC 690275, EPU Phase Implementation

For Information Only TP-1 62-030 Revision 0 Page 6 of 25

4.

TEST EQUIPMENT None

5.

PRECAUTIONS 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 Start-up Test Supervisor 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.

6.

PREREQUISITES 1

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)

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 9

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

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 7 of 25 6.4 Confirm the following data collection systems are available to collect data in support of this TP:

o3 6.4.1 GE Data Acquisition System (DAS) is functional o

6.4.2 PPL VDAS is functional o

6.4.3 PPL VXI is functional O

6.4.4 PPL Extraction Steam DAS is functional Confirmed By O

6.5 Shift Supervision concurs with the start of this TP.

Shift Supervision O

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 Steam Dryer Instrumentation/Data Acquisition/Analysis 0

7.1.1 Collect GE steam dryer data set(s), in accordance with TP&P 3146, for the specified time frame.

Confirmed By

For Information Only TP-162-030 Revision 0 Page 8 of 25 O

7.1.2 GE to Confirm data set collected is adequate for analysis.

Confirmed By O

7.1.3 GE to Analyze and Trend data set(s) in accordance with TP&P 3146.

Confirmed By o

7.1.4 GE to Submit analyzed data report to EPU Engineering for incorporation into the Test Point Report.

Confirmed By 7.2 MSL Strain Gages (SGs) o 7.2.1 Collect MSL SGs data set(s), using the VXI 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) in accordance with GE-NE-0000-0080-8732-P-R1.

Confirmed By o

7.2.4 Incorporate the data set(s) into Test Point Report.

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 9 of 25 7.3 MSL Accelerometer Data Acquisition/Analysis (Line B & C)

O3 7.3.1 Collect MSL Ac-celerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By O3 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 O

7.3.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.4 Feedwater Loop A Accelerometer Data Acquisition/Analysis o

7.4.1 Collect FW Loop 'A' Accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By o

7.4.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By O

7.4.3 EPU Engineering to Analyze and Trend data set(s) against criteria provided in Attachment C.

Confirmed By

For Information Only TP-162-030 Revision 0 Page 10 of 25 O

7.4.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.5 Recirculation/RHR Strain Gage Data Acquisition o

7.5.1 Collect Recirculation/RHR strain gage data set(s), using the VXl equipment, for specified time frame.

Confirmed By o

7.5.2 Confirm data set is acceptable for submitting to EPU Engineering.

Confirmed By 7.6 Recirculation Loop A & B Accelerometer Data Acquisition/Analysis o3 7.6.1 Collect Recirculation Loop A & 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 O

7.6.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment C.

Confirmed By 0

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

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 11 of 25 7.7 RHR Valve HV151FO15A(B) and HV151FO17A(B) Accelerometer Data Acquisition/Analysis O

7.7.1 Collect RHR valves HV151FO15A(B) and HV151FO17A(B) accelerometer data set(s), using the VDAS equipment, for specified time frame.

Confirmed By o3 7.7.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By o

7.7.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment E.

Confirmed By 17 7.7.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By 7.8 Extraction Steam Accelerometer Data Acquisition/Analysis o

7.8.1 Collect Extraction Steam Accelerometer data set(s), using the tape recording equipment, for specified time frame.

Confirmed By O

7.8.2 Transfer data set(s) information from tape recording to VDAS.

Confirmed By O

7.8.3 Confirm data set(s) is acceptable for submitting to EPU Engineering for analysis.

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 12 of 25 0

7.8.4 EPU Engineering to Analyze and Trend data set(s) against criteria provided In Attachment D.

Confirmed By EJ 7.8.5 Submit analyzed data set (s) for incorporation Into Test Point Report.

Confirmed By 7.9 Locally Monitored Acceleration Data Acquisition o

7.9.1 Collect locally monitored acceleration data set(s), using the hand held equipment, for specified time frame.

Confirmed By o

7.9.2 Confirm data set is acceptable for submitting to EPU Engineering for analysis.

Confirmed By O

7.9.3 EPU Engineering to Analyze data set(s) against criteria provided in Attachment D.

Confirmed By o

7.9.4 Submit analyzed data set(s) for incorporation into Test Point Report.

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 13 of 25 7.10 Accessible Area Walkdowns 13 13 11 NOTE:

Not all walkdowns identified in Part C, Table 1, of EC-PUPC-2069 must be performed each time.

7.10.1 Perform walkdowns of areas specified in Part C, Table 1, of EC-PU PC-2069.

Confirmed By 7.10.2 Evaluate walkdown results against criteria provide in Part C of EC-PUPC-2069.

Confirmed By 7.10.3 Confirm the specified area walkdowns are complete and results have been submitted for Test Point Report.

Confirmed By In-Accessible Area Walkdown NOTE:

Not all walkdowns identified in Part 0, Table 1, of EC-PUPC-2069 must be performed each time.

7.11 03 7.11.1 Perform walkdown of areas specified in Part D, Table 1, of EC-PUPC-2069 for this Test Point.

Confirmed By Evaluate walkdown results against criteria provide in Part D of EC-PUPC-2069.

01 7.11.2 Confirmed By

?or Information Only TP-1 62-030 Revision 0 Page 14 of 25 Q

7.11.3 Confirm the specified area walkdowns are complete and results have been subpitted for Test Point Report.

Confirmed By 7.12 Pi Data Sheet Acquisition 0

7.12.1 Determine start and finish times for the data set(s).

Confirmed By O

7.12.2 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 o

7.12.3 Submit the Pi Data Sheet to EPU Engineering for analysis.

Confirmed By O

7.12.4 Submit analyzed Pi Data Sheet for incorporation into Test Point Report.

Confirmed By 7.13 Ol-TA-008 Data Acquisition O

7.13.1 Collect data set in accordance with Attachment F of OI-TA-008 for the time frame(s) specified.

Confirmed By 13 7.13.2 EPU Engineering to review the O-TA-008 data for abnormal instrument readings.

Confirmed By

For Information Only TP-1 62-030 Revision 0 Page 15 of 25 Submit OI-TA-008 data for incorporation into Test Point Report.

01 7.13.3 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.

Q 9.1 Steam dryer instrumentation data meets the Level 1 and Level 2 Acceptance Criteria specified in GE-NE-0000-0080-2994-P-R4 for this Test Point.

Level 1 Met (Yes/No)

Level 2 Met (Yes/No)

Confirmed By f

9.2 MSL SGs data has been analyzed and has been benchmarked against the MSL Limit Curves supplied in GE-NE-0000-0080-8732-P-R1 for this Test Point.

Confirmed By Q

9.3 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

For Information Only TP-1 62-030 Revision 0 Page 16 of 25 Q

9.4 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

9.5 Recirculation Loop A & 8 accelerations meet the Level 2 Acceptance Criteria specified in Attachment C for this Test Point.

Level 2 Met (Yes/No)

Confirmed By fl 9.6 RHR Valves HV1 51 F01 5A(B) and HV1 511F01 7A(B) accelerations meet the Screening Criteria specified in Attachment E for this Test Point.

Screening criteria met.

(Yes/No)

Confirmed By Q

9.7 Extraction Steam accelerations meet the Level 1 and Level 2 Acceptance Criteria specified in Attachment D for this Test Point.

Level 1 Met (Yes/No)

Level 2 Met (Yes/No)

Confirmed By Q

9.8 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-1 62-030 Revision 0 Page 17 of 25 S

9.9 Walkdown of Accessible Areas specified in Part C, Table 1.0 of EC-PUPC-2069 are acceptable per the requirments specified in Part C of EC-PUPC-2069 for this Test Point.

Confirmed By o]

9.10 Walkdown of the In-Accessible Areas specified In Part D, Table 1.0 of EC-PUPC-2069 are acceptable per the requirements specified in Part D of EC-PUPC-2069 for this Test Point.

Confirmed By O

9.11 Pi data Sheets have been analyzed and exhibit no signs of abnormal readings for the specified Test Point.

Confirmed By IJ 9.12 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-162-030 Revison 0 Page 18 of 25 0

H I-h 0

0 c-i REQUIRED TESTING p of Data Locally Steam Recirc/RHR A csMonitored Test Points Steam Steam Dryer Recirc/

Vlvs F015& Extraction Accessible In-accessible Aooed Dryer Dryer Press MSt.

FW RHR Recirc F017 Steam Area Area Pi Data Collectton SGs Accels Sensors MSL SGs Accels AcceLs SGs Accels Accets Accels Walkdown Walkdown Sheet Ot-TA-0,08 Note 6

-673 MWi (16%);Bkr Closure YES YES YES YES YES YES

-1300 MWt (38%); Scram Time Testing YES' YES YES YES YES

-1976 MWt (50%)

Y=5 YES YES YES YES YES

-2569 iWt (65%); Start 3" RFP YES YES YES YES YES YES YES YES YES YES YES YES

-2873 MWt (72.7%); Pre-MSIV Closure YES YES YES YES YES YES YES Note 1 YES YES YES YES YES Note YES YES YES YES YES 2873MWt(72.7%)MSIVClosed Note3 Note3 Note3 3

Note3 Note3 Noteo3 Note1&3 Note3 YES

-3039 MWT (76.9%); Prc-MSIV Closure YES YES YES YES YES YES YES Note 1 YES YES YES YES YES Note YES YES YES YES YES 3039MWt(76.9%)MSIVCIoscd Note3 Note3 Note3 3

Note3 Note,3 Note3 Note1&3 Note3

-3293 MWt (83.3%):

YES YES YES YES YES

-3489 M*s (88.2%)

YES YES YES YES YES YES YES YES YES YES YES Initial Power increases between 3489 and 3611MWt YES YES YES YES YES YES YES YES YES Note YES YES (Hourly readings)

Note 5 Note 5 Note 5 Note 5 Note 5 Note 5 Note 5 Note 5 5

Note 5 Note 5I

-3611F M1t(91.3%)

YES YES YES YES YES YES YES YES YES YES YES Initia Power increases between 3611 and 3733 MvWt YES YES YES YES YES YES YES YES YES Note YES YES (Houdy readings)

Note 5 Note S Note 5 Note 5 Note 5 Note 5 Note 5 Note 5 5

Note 5 Note 5 3733 MWt (94.4%) with 100 MlblI-r Care Flow YES YES YES YES YES YES YES YES YES YES YES 3733 MWt (94.4%) 91MIb*r YES YES YES YES YES YES YES YES Test Condition 'U' 100 to 108 MIb/Hr Core Flow (every Mlb/Hr up to 105MIb/Hr & evcey 0.5Mlb/Hr YES from 105 to 108MINWHr)

YES YES YES YES Note 2 YES YES YES YES YES YES 3733 MWI (94.4%) 108 Mi/Hr YES YES YES YES YES YES YES YES 3733 MWt (944%) Target Core Flow YES YES YES YES YES YES YES YES YES YES Note 1: Only perform the Inspections of the HPCI and RLIC PER Part C Note 2: Continuously monitor and recoreded the MSL Accelerometers during core flow sweep looking for Resonance frequencies.

Note 3: Data Collection and confirming data acceptable for analysis will be signed off following each MSIV closure, Analyzing and Submittal of results will be signed off after all four MSIVs have been closed.

Note 4: Data Collection at each Test Point can be added, as deemed necessary, during the Start-up tasting. Attachment identifies the minimum required.

Note 5: This data is collected only this data is not for analysis during the increase in power to 3611(3733) MWL Data will be Inclu.ded in the Tesr Point Report, along with the data collected and analyzed at Test Point 3611(3733) MWt.

Note 6:Enter a YES in this column if visual observation indicates the need for more quaintative analysis of a non-instrumented piping run.

Page 1 of 1

DATA COLLECTION/ANALYSIS SUPPORT Attachment B TP-162-030 Revision 0 Page 19 of 25 0

H 1-h 0

rrH-.

0 Responsible Responsible Responsible For Data Responsible Data Collection Responsible for Ready to for Data Analyzed/

for Data Description Organization Collect Data Collected Reviewed Submitted Comments Per GE Steam Dryer GE/EPU EPU Proprietary Instrumentation GE GE GE Engineering Engineering Documents EPU EPU No Acceptance MSL SGs PPL PPL PM PPL PM Engineering Engineering Criteria MSL, FW EPU EPU EC-PUPC-2069 Accelerometers PPL PPL PM PPL PM Engineering Engineering Part A Recirculation Sys Design Design EC-PUPC-2069 Accelerometers PPL PPL PM PPL PM Engineering Engineering Part A Design Design No A'eptance Recirculation/RHR SGs PPL PPL PM PPL PM Engineering Engineering Criteria RHR VIvs HV151FO15A(B) &

HVI51FO17A(B)

Design Design EC-PUPC-2069 Accelerometers PPL PPL PM PPL PM Engineering Engineering Part E Extraction Steam EPU EPU EC-PUPC-2069 Accelerometers PPL PPL PM PPL PM Engineering Engineering Part B Accessible Area EPU EPU EPU EPU EC-PUPC-2069 Walkdown PPL Engineering Engineering Engineering Engineering Part C In-Accessible Area EPU EPU EPU EPU EC-PUPC-2069 Walkdown PPL Engineering Engineering Engineering Engineering Part 0 EPU EPU EPU EPU Pi Data Sheet PPL Engineering Engineering Engineering Engineering 01-TA-008 PPL On Shift STA On Shift STA On-Shift STA On-Shift STA Locally Monitored Design Design EC-PUPC-2069 Acceleration Data PPL PPL PM PPL PM Engineering Engineering Part B Page 1 of 1

For Information Only Attachment C TP-1 62-030 Revision 0 Page 20 of 25 Guidelines to Evaluate Data Set(s) for Accelerometers Located Insidq.the Drywell NOTE:

Steps of Attachment C should be followed sequentially.

A.

MSL B. MSL C and FW LoopA

1.

Refer to Part A, Table 1,0 of EC-PUPC-2069 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-2069.

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-2069 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), THEN 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-2069 for Level 1 acceptability.

9.

If the data set(s) accelerometer values are less than the Level I 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-162-030 Revision 0 Page 21 of 25

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-2069 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-2069.

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 0 values.

5.

If the data set(s) accelerometer values are less than the Level B 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-1 62-030 Revision 0 Page 22 of 25 Guidelines to Evaluate Data Set(s) for Accelerometers Located Outsidce the Drywell NOTE:

Steps of Attachment D should be followed sequentially.

A.

Extraction Steam Accelerometers;

1.

Refer to Part B, Table 1.0 of EC-PUPC-2069 for quick reference Level C(D) and Level A(B) Acceptance Criteria for the Extraction Steam Accelerometers.

2.

Evaluate data set(s) against the quick reference Acceptance Criteria of Part B, Table 1.0 of EC-PUPC-2069.

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, THE.N 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 B, Table 1.2 of EC-PUPC-2069 for Level 2 acceptability.

6.

If the data set(s) accelerometer values are less than the Level 2 values specified in Table 1.2, THEN 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 B, Table 1.1 of EC-PUPC-2069 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.

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.

Page 1 of 2

?or Information Only Attachment D TP-1 62-030 Revision 0 Page 23 of 25 B.

Locally Monitored Acceleration Data:

1.

Refer to Part B, Table 2,0 of EC-PUPC-2069 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 2.0 of EC-PUPC-2069

3.

if the data set(s) accelerometer values are less than the Level 2 values specified in Table 2.0, 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 2.0, THEN EPU Engineering to Evaluate the data set(s) values and issue AR.

Page 2 of 2

For Information Only Attachment E TP-1 62-030 Revision 0 Page 24 of 25 Guidelines For Evaluation Of Data Set(s) For RHR HV151F015A(B) &

HV1 51 F017A(B) Accelerometers

1.

Refer to Part E of EC-PUPC-2069 for Quick Look Screening Criteria for the RHR HV1 51 F01 5A(B) & HV151 F017A(B) valve accelerometers.

2.

Evaluate data set(s) against the quick reference Acceptance Criteria of Part E of EC-PUPC-2069.

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 of EC-PUPC-2069, THEN the Screening Criteria data set(s) MEET the Acceptance Criteria for this Test Point.

Page I of 1

For Information Only Attachment F TP-1 62-030 Revision 0 Page 25 of 25 Pi STEAM DRYER DATA LOG SHEET (Information to be contained in Pi Print-out)

Date/Time

!W*

Test Point COMPUTER ID VALUE UNITS Thermal Power (Instantaneous) p01.nba01 MWth Thermal Power (15 Min Ave.)

01.nba01 I MWth Electrical Power p01.tra178 MWe Total Core Flow p01.tra026 MlbnVhr Recirc Loop Flow A p01.tra028 Mlbm/hr Recirc Loop Flow B U01.tra029 Mlbm/hr Core Plate D/P p01.traO27.....

_PSI Steam Flow Line A p01.tral 53 Mlbm/hr Steam Flow Line B p01.tral 54....

Mlb.rhr Steam Flow Line C p01.tral 55 Mlbmrnhr Steam Flow Line D p01.tral 56 Mlbm/hr Total Steam Flow p01.traO97 Mlbm/hr Feedwater Flow w01.tra098 Mlbmlhr Feedwater Temperature Line A p01.tra102 "F

Feedwater Temperature Line B p01.tral03 "F

Feedwater Temperature Line C p0l.tral04 TF Rx Dome Press Narrow Range p01.tra2O8 PSIG Rx Dome Press Wide Range pOl.tra2O9 PSIG Steam Dome Temperature pO 1.nfaO5

F Recirculation Pump A Speed vm. 1p401a/la-rrptac RPM Recirculation Pump B Speed vm.1 p401 b/1 brrp-jac RPM Recirculation PumpA Power pOl.nrj5l MWe Recirculation Pump B Power p01.nrj52 MWe CRD Cooling Header Flow p01.nefO3 GPM CRD System Flow

.01.nefl01 GPM CRD System Temperature p01.ndtO5

F Bottom head Drain Temperature i1:.tra206 T_

Rx Water Level Narrow Range p0l.tra142 Inches H20 Rx Water Level Narrow Range p01.nf102 Inches H20 Rx Water Level Narrow Range p01.nf103 Inches H20 Rx Water Level Wide Range p0l.tra143 Inches H20 Recirc.Pmp A vane passing Freq n/a Hz Recirc Pmp B vane passing Freq n/a Hz Recirc Pmp A Motor Freg n/a Hz Recirc Prop A Motor Freg n/a Hz Page 1 of 1

For Information Only PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE SHIFT TECHNICAL ADVISOR RESPONSIBILITIES OI-TA-008 Revision 9 Page 1 of 23 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:

Assistant Operations Manager -

Shift Operations 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 9 Page 2 of 23 TABLE OF CONTENTS SECTION

1.

PURPOSE

2.

RESPONSIBILITIES

3.

REFERENCES

4.

DEFINITIONS

5.

INSTRUCTIONS

6.

RECORDS PAGE 3

3 8

9 9

13 ATTACHMENTS ATTACHMENT A

B C

D E

F STA Assessment Guide STA Routine PICSY Display Turn On Codes STA Action Guidelines Off Normal Procedures Unit 1 RPV Steam Dryer Structural Monitoring PAGE 14 16 17 18 20 21 I

For Information Only OI-TA-008 Revision 9 Page 3 of 23

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 informati-on Only 01-TA-008 Revision 9 Page 4 of 23 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 reactor for attainment and maintenance of adequate core 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.

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

For Information Only O1-TA-008 Revision 9 Page 5 of 23

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 0I-TA-008 Revision 9 Page 6 of 23

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 1000 F/hr cool down limitation. Assist Shift Supervision in developing a plant cool down strategy within the limits designated in the Unit Technical Specifications (<1000F/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 OI-TA-001, "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 OI-TA-008 Revision 9 Page 7 of 23 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 Performing duties as the on shift procedure coordinator. This includes complete management of procedure reviews and revisions (including upgrades to meet OI-AD-055 standards).

NDAP-OA-0002 provides comprehensive instructions for preparation of new, changes to existing, and deletion of existing Operations Functional Unit Procedures. OI-AD-055 includes details on standards for Operations procedures, including format, content, etc.

2.3.10 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.

2.3.11 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.

2.3.12 Performing Peer Checks when requested.

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

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

For Information Only OI-TA-008 Revision 9 Page 8 of 23 2.3.15 Reviewing Industry Operating Experience and providing information for use in conducting Pre-Job Briefs as requested by Operations Supervision and/or PCO's.

2.3.16 Performing the duties of PORC Secretary (in accordance with NDAP-QA-0006) in cases where personnel normally performing this duty are not available (e.g., nightshifts and weekends). STA's may also participate as an Alternate Member of PORC as needed.

2.3.17 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 OI-AD-040.

2.3.18 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 Nuclear Operations Supervisor-Operations Engineering 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 OI-AD-001, Administrative Control of Operations Instructions 3.11 OI-AD-055, Operations Procedure Program

For Information Only O-TA-008 Revision 9 Page 9 of 23 3.12 OI-AD-055, Procedure Writer's Guide 3.13 QI-AD-040, System Status File Audits

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

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.

For Information Only OI-TA-008 Revision 9 Page 10 of 23 5.1.7 Both the Offgoing and Oncoming STAs will sign the STA Turnover Sheet to document transfer of responsibilities.

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 Control Room panel indications (2)

Reviewing the LCO/TRO logs.

(3)

Reviewing the PCO logs.

(4)

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:

(1)

Surveillance Procedures SO-1 00/200-006, SO-1 00/200-007, and SO-1 00/200-008 have specific signoffs documenting STA review.

e.

Review POWERPLEX II 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-100/200-003.

f.

Review the STA's Plant Parameter P1 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.

For Information Only 1O-TA-008 Revision 9 Page 11 of 23

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.

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.

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 (4)

The STA will also provide a summary of Risk Status changes at Mid-Shift and End-of-Shift Briefings (including the reason for the changes and any impacts relative to Protected Equipment).

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.

For Information Only O-TA-008 Revision 9 Page 12 of 23

b.

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

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 Steam Dryer Structural Integrity via Pl.

Attachment F contains 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 Supervisor Operations Engineering-SSES.

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 O1-TA-008 Revision 9 Page 13 of 23

6.

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

For Information Only Attachment A OI-TA-008 Revision 9 Page 14 of 23 STA ASSESSMENT GUIDE STA ASSESSMENT GUIDE SHEET 1 INITIAL EVENT PICSY DISPLAYS E3 TRA Initiated TRASTS, TRATRIG Li Check All Rods In 0D7 El Verify Isolations, Initiations, and D/G Starts CONTISO Li SDV Vents and Drains Li Main Turbine Speed decreasing TRBB E3 Check Rx Vessel Level PRIMARY Li Check Rx Vessel Pressure PRIMARY, RPRESS EL SRV Lifts SRV,_CONTN Li Check Containment Parameters CONTN Li Check Rad levels RADEFF

[] Verif MSL Rads trended down with Power ERADMON

[L Verify E-Plan Entries (15 Min)

Li Evaluate the need for a PAR.

A PAR must be made for General Emergency.

[I VeriftyENS Notification (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

Reactivity Control E]

Rx Power >102% (Unit 1 3807 MWth, Initiate SBLC i Inhibit ADS:

NBA01, NBA08 Unit 2 3509 MWth - NBA01)

>5% Initial Power-0D7 Li More than 1 Control Rod > 00 Immediately, PRIMARY, CORESTAT Initial Reactor Power 5% Initial Power -

PRIMARY, ECCSFL Li Rx Power> 5%

Before SP Temp =1 501F STA

[I Recirc Pumps Tripped EL Init SBLC/Inhibit ADS C Power Decreased w/ lowering level Li Pressure maintained >800#

0 ADS & LP ECCS Inhibited Li RPS De-energized?

Li Hydraulic Lock?

Li CRD Available?, Cross-tie?

Li Alt Insertion methods in Progress?

Rx Vessel Level Control Level Set points reached?

Auto Actuation's RWTLVL, ECCSFL, STA 0i Level 8, +54"

+54 Main Turbine Trip Li Level 3, +13", Auto Act. Complete RRP's Trip "i Level 2, -38", Auto Act. Complete

+ 13 RX SCRAM, RRP (30%)

Li Level 1, -129", Auto Act. Complete

-30 RCIC EL WR -145", Transition to Fuel Zone

- 38 ARI, HPCI, SBGTS, El Below TAF, -161" CREOASS, ISO RWCU, FUELZONE Loss - Coolant System Boundary RRP Trip (1Os TD)

EOF, STA Potential Loss - Fuel Clad Boundary

-129 CS, RHR, D/G, C3 Below TAF, - 205", Loss Fuel Clad ESW, ADS Timers, Boundary Airborne Release MSIV closure Li Fuel Zone < - 290" - Level Indeterminate EL Adequate Core Cooling?

System Design Flow ECCSFL, STA L] Submergence, >-161" Cond/FW 28,800 gpm

[I Steam Cooling, > -205" (Non-AIWS)

HPCI 5000 gpm Li Systems Injecting RCIC 600 gpm EL Cond I Feedwater RHR Loop 21,300 gpm Ri HPCI CS Loop 6,350 gpm

[I RCIC SBLC 43gpm EL RHR Loop'A' CRD 63 gpm El RHR Loop'B' Li Core Spray Loop 'A' Li Core Spray Loop 'B' Li SBLC Li CRD Page 1 of 2

For Information Only Attachment A oI-TA-008 Revision 9 Page 15 of 23 STA ASSESSMENT GUIDE STA ASSESSMENT GUIDE SHEET 2 12v Dric~eeram Crntrnt I

El MSIV's Open ARI - 1135#

CONTN, SRV

[l Bypass Valves & Condenser Available EOC-RPT - SV Closure (5.5%)

El MSIV's Closed CV Fast Closure (500# ETS)

PRIMARY, RPRESS El SRV's Cycling SRV Safety Setpoints CONTN C1 RHR in SPC Condenser Vacuum Trips Pressure Setpoints reached?

Main Turb. Unit 1-8.0" HgA USOPSTS o 1087#

(21.2" HgV)

El 861#, MS in Run Unit 2-7.5" HgA El 700#

(21.7 HgV) 0l Condensate Available RFPT 11.8" HgA (17.4" HgV)

El 420#

MSL 19.0" HgA (10.2" HgV)

C1 ECCS Overridden if not Req.

BPV's 22.2" HgA (7.0" HgV)

Containment Integrity 0l Containment Isolations Complete?

Curves CONTISO El Primary Containment Challenged?

PSL-PRESSUPP CONTN El Supp Pool Temps"F (>90*F)

HCTL - HEATCAP EOF, STA, STEMP El 90*F, RHR in SPC SAT - RPVSAT El 140°F, Bypass HPCI Swap HEATCAP

[] 150°F Monitor HCTL El 2300F, use RHR for SP Temps PRESSUPP El Supp Pool Level - (<22',>24')

[1 38', RD El 26', Initiate HPCI/RCIC 0l 22', ECCS Rooms Flooded E] <21', Monitor Vortex Umits

[] <20.5' SPOTMOS lower sensors El 17', Isolate HPCI (Before 17')

Vortex Limits STEMP E] 12', RD (Before 12' Non ATWS)

RHR - 18' El DW Press (>1.72#)

CS

-15.5'to2l' 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 0

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

0 H202 Levels (>4%)

RHR, CS Init. if <420#

0l DW Temp (>1500F)

RHR, SPC/SPS/DWS Isol El

>212 0F, monitor SAT curve HPCI PCM Swap to Inj RPVSAT El 3400F (Before), Spray DW DW Sprays

[] > 3400F, RD

>13# Supp Chamber

[] Secondary Containment challenged?

Before DW Temp = 340°F El ARM Alarms EO104, RADRX El Room Temps RDPAM El Fire Detection El 749' 4&5 racks-WR -125" to +60" 749' Fire Zones, 4 & 5 racks Ul - X218_Z7 U2 - X232_Z5 Radioactive Release El Radiation Release in progress Unusual Event (60 min)

RADEFF El Monitored, (SPINGS Available)?

Noble Gas 2.OE+6.Cl/min METVENT1 (15 min ave) 0l Unmonitored, Dose Calc's performed?

Iodine/Part 3000 mRem/Yr El Fuel Damage Indicated Alert, E0105 (15 min)

CONTN El Containment Rads increasing?

Noble Gas 2.OE+8 pCi/min E_RADMON E] 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+8liCi/min CSRWE, RDPAM, El Blowout Panels Checked, Security General RADMS Noble Gas 6.2E+9gCVmin I1 Page 2 of 2

For Information Only Attachment B OI-TA-008 Revision 9 Page 16 of 23 STA ROUTINE DAY SHIFT Attend Shift Briefing Station Status Report Updates (markups)

Clear SPDS Isolations Review PCO Logs Review STA Log Review LCO/TRO Logs Update Turnover Sheet Review Ops Shiftly, Daily & Weekly Surveillances Review the STA's Plant Parameter PI 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)

NIGHT SHIFT Attend Shift Briefing Station Status Report Updates for Work Management (issue reports on weekends and holidays when Work Management is not available)

Clear SPDS Isolations Review PCO 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 Ops Shiftly, Daily & Weekly Surveillances 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 Steam Dryer Structural Integrity Page 1 of 1

For Information Only Attachment C OI-TA-008 Revision 9 Page 17 of 23 PICSY DISPLAY TURN-ON CODES FEEDWATER HEATERS 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)

COF MAIN TURBINE FORMATS MAIN GENERATOR ELECTRICAL DIST Stop/Control Valves TBVLV Main Generator MNGEN 13.8 kv System 13KV HP Turbine HPTB Gen/Alternator clng GENCL Aux buses AXB12 HP Turb Performance HPPR DIESELS Startup bus 10 SUIO Moisture Separators WTRSP D/G A DG-A Startup bus 20 SU20 LP Turbine A LPTBA D/G 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 1 Lube OilIBmg temps TBLO Lube OiVEHC LOEHC Vib/Bmg metal temp TBVIB Sealing Steam TBSST CONTAINMENT REACTOR RAD MONITORING Containment Status Containment Isolations PSL Curve HCTL Curve SAT Curve Cont temps/press,SP level SP Water temp/map,SRV status SP water temp/SPOTMOS SW/RB/TB sumps DW fans/coolers/RB chillers CONITN CONTISO PRESSUPP HEATCAP RPVSAT CTATM SRVTEMP STEMP LRW RBWT Rx Cooldown A B

Rx Heatup A

B Shutdown params LPRM's SRM/1RM Overlap IRM/APRM Overlap Reactor Parameters Reactor Water LvI Reactor Core Status RCDA RCDB RHUA RHUB SHOWN LPRM NMSAE NMSC EOF RWTLVL CORESTAT Rx Bldg Tb Bldg CS, RW & Admin CS & RW Misc Hi range ARM's Process Rad EO-104 Table #9 Spings Spings (15 Min Avg)

RADRX RADTB RADMS CSRWE GD ECSRAD RDPAM GD ERADMON E0104 RADEFF ME'VENT1 a

VVPl r- -a 0701 Mo MIU Service water Circ water Circ wtr pp mtr RBCCW TBCCW ESW RHRSW GRRCCW RBCW CS, TB HVAC RWMU Cond xfr, Refuel SPWTR CIRWT CWPMT RBCCW TBCCW EWSTR RHR GRCCW RBWT CSTB MUPWT CDRF Unit Performance Chemistry CDI/FW cond trend RWCU/Recirc cond trend Environmental Cond Emergency Format HWC-H2 Flow HWC-02 Flow CFS STA Overview UPERF CYCHM CFW RXWC ENVIR EOF HYDROGEN OXYGEN CFS STA Page 1 of 1

For Information Only Attachment D OI-TA-008 Revision 9 Page 18 of 23 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 B Backup Emergency Plan calls

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-103

" 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-103 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 9 Page 19 of 23 EVENT INITIAL EVALUATIONS Ensure TRA tripped Power SBLC Injection Pressure Level Containment Rad Releases DG starts ESW starts ESS power Offsite power Emergency Plan Reportability Makeup sources Heat Sinks BOP Isolations 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?

RWCU isolated?

Pumps running; injecting and flow?

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

ECCS initiations or anticipated, EO entry?

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

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

Voltage, frequency, output breaker/bus voltages?

Ensure DG and ECCS room cooling Ensure started manually if HPCl/RCIC auto-start on level Busses 1 A thru 1D and 2A thru 2D available?

Start Up Bus 10 and 20 powered?

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

1,4, 8 or 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ?

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

MSIV's Condenser, Circ Water, Bypass Valves, Supp Pool temp Condenser, Circ Water, Service Water, Instrument Air, rad levels, HVAC configuration SPDS and ON-I59-002 or ON-259-002 Page 2 of 2

For Information Only Attachment E OI-TA-008 Revision 9 Page 20 of 23 OFF NORMAL PROCEDURES SCRAM/TRIP:

ON-100-101 SCRAM, SCRAM Imminent ON-158-001 Loss of RPS ON-193-002 Main Turb Trip ON-183-001 Stuck Open SRV ON-184-001 MS Line Isot & Quick Recovery REACTIVITY:

I "

ON-100-004 Rx Power > Authorized Limit ON-100-006 Loss of Reactor Heat Balance Calculation ON-147-001 Loss of FW Htg Extr Stm ON-147-002 Loss of FW Htg String ON-155-001 Control Rod Problems ON-155-004 RPIS Failure ON-155-007 Loss of CRD System Flow ON-156-001 Unexplained Reactivity Chg ON-164-002 Loss of Recirc Flow ON-164-003 Recirc Pp Dual Seal Failure ON-178-002 Core Flux Oscillations ON-193-001 Turb EHC Malfunction ELECTRICAL:

ON-003-001 Loss of SUB 10 ON-003-002 Loss of SUB 20 ON-004-002 Energizing Dead 4KV Bus ON-024-001 D/G Trip ON-102-610 Loss of 125 VDC Bus 1D610 o

ON-1 02-620 Loss of 125 VDC Bus 10620 o

ON-1 02-630 Loss of 125 VDC Bus 10630 ON-1 02-640 Loss of 125 VDC Bus 10640 ON-103-001 Grid Instabilities ON-1 03-003 Aux Buses 11A/B Loss/UV Shed ON-104-001 LOOP-U1 Response ON-104-201 Loss of 4KV Bus 1A (1A201)

ON-104-202 Loss of 4KV Bus 1 B (1A202)

ON-104-203 Loss of 4KV Bus 1C (1A203) o ON-104-204 Loss of 4KV Bus 1D (1A204)

ON-1 17-001 Loss of Instrument Bus ON-175-001 Loss of 24 VDC Bus ON-188-001 Loss of 250 VDC Bus COOLING:

ON-009-001 Loss of RWMU ON-030-001 Loss of CS Chilled Water ON-054-001 Loss of ESW ON-i 11-001 Loss of Service Water ON-1 14-001 Loss of RBCCW ON-115-001 Loss of TBCCW ON-133-001 Loss of TBCW ON-134-001 Loss of RBCW 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 CONDENSER/VACUUM:

ON-070-002 Hi, Hi H2 Concentration in Common Offgas RCB Discharge ON-142-001 Circ Water System Leak ON-143-001 Main Condenser Vacuum & Offgas Sys Off Normal Operation ON-172-002 Hi Hi H2 Concentration in Unit 1 Offgas RCB Discharge CIG/INSTRUMENT AIR:

ON-1 18-001 Loss of Instrument Air ON-125-001 Loss of CIG PRIMARY CONTAINMENT:

ON-100-005 Excess DW Leakage ON-159-002 Containment Isolation ON-159-003 PC Water Level Anomaly MAIN GENERATOR:

ON-198-001 MVAR Cntl, Auto Volt Reg. Sync'd to Grid ON-198-002 MVAR Cntl, Manual Volt Reg. Sync'd to Grid ON-1 98-003 Mn Gen Connected Single Phase to Grid @ S/U ON-1 98-004 Mn Gen Unable to Disco. from Grid After a TT RPV LEVEL:

ON-1 45-001 RPV Lvl Cntrt Malfunction ON-1 45-004 RPV Water Level Anomaly ON-1 44-001 Emergency Operation of Condensate System HVAC:

ON-030-002 Loss of CS HVAC ON-134-002 High/Low RX Bldg DP RADIATION:

ON-069-001 Abnormal Rad Rel - Liquid ON-070-001 Abnormal Gas Rad ReVCAM Alarms ON-1 79-001 Increasing Offgas MSL Rad Levels FUEL:

ON-081-001 Fuel Handling Accident ON-081-002 Refueling Platform Operation Anomaly FIRE/FLOOD:

ON-013-001 Fire ON-169-001 TB Flooding ON-169-002 RB Flooding WEATHER:

ON-000-002 Natural Phenomena ON-100-102 Unit 1 Hot Weather MISCELLANEOUS:

ON-000-010 Security Event ON-037-001 Loss of Condensate Transfer ON-089-001 Dry Fuel Storage Temp Anomaly ON-100-003 Chemistry Anomaly ON-100-009 Control Rm Evacuation ON-144-002 Condensate Filtr Anomaly Page 1 of 1

For Information Only Attachment F OI-TA-008 UNIT 1 RPV STEAM DRYER Revision 9 STRUCTURAL INTEGRITY MONITORING Page 21 of 23 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 Monitoringq 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-B21-1D002

a.

NFP03 RPV Wide Range Press

b.

NFLO4 Rx Upset Range Lvl 517" variable tap

c.

NFL05 RPV Extended Range Lvl 366" variable tap

3.

Condensing Chamber XY-B21-1D004A

a.

NFP05 RPV Wide Range Press

b.

NFL02 Rx Narrow Range Lvl B 517" variable tap

c.

NBL05 RPV Wide Range Lvl 366" variable tap

4.

Condensing Chamber XY-B21 -1 D004B

a.

NFP51 Reactor Pressure SRU 4

b.

NFL03 Rx Narrow Range Lvl C 517" variable tap

c.

NBL06 RPV Wide Range Lvi 366" variable tap

5.

Condensing Chamber XY-14202

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 3

For Information Only Attachment F 01-TA-008 UNIT 1 RPV STEAM DRYER Revision 9 STRUCTURAL INTEGRITY MONITORING Page 22 of 23 Backgiround 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 flow 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 2 of 3

For Information Only Attachment F 01-TA-008 UNIT 1 RPV STEAM DRYER Revision 9 STRUCTURAL INTEGRITY MONITORING Page 23 of 23 References

1.

GE SIL No. 644 Rev 2 BWR Steam Dryer Integrity

2.

GE SIL No. 644 Supplement 1 BWR Steam Dryer Integrity

3.

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PLA-6351, Transmittal of Startup Test Procedures Pursuant to License Conditions 2.C. (36) (B) 8 and 2.C. (36) (C)

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SUMMARY

SUMMARY

SUMMARY

C. PROCEDURE

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PLA-6351, Transmittal of Startup Test Procedures Pursuant to License Conditions 2.C. (36) (B) 8 and 2.C. (36) (C)

Text

SUMMARY

SUMMARY

SUMMARY

C. PROCEDURE

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