PLA-6715, Extended Power Uprate Master Test Procedure Supplement, Renewed Operating License No. NPF-22, License Condition 2.C.(20)(c), PLA-6715

Extended Power Uprate Master Test Procedure Supplement, Renewed Operating License No. NPF-22, License Condition 2.C.(20)(c), PLA-6715

ML111101428
Person / Time
Site:	Susquehanna
Issue date:	04/20/2011
From:	Rausch T Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6715, TP-299-010
Download: ML111101428 (74)

Text

Timothy S. Rausch PPL Susquehanna, LLC Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542_1504 tsrausclqppiweb.corn PP U. S. Nuclear Regulatory Commission Attn: .Docum.ent Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 EXTENDED POWER UPRATE MASTER TEST PROCEDURE TP-299-010 SUPPLEMENT RENEWED OPERATING LICENSE NO. NPF-22 LICENSE CONDITION 2.C.(20)(c)

PLA-6715 Docket No. 50-388 Reference. PGA-66.97, Afr. T .Rausch (PPL) to Document Control Desk (USNRC),

"Unit 2 &tended Power Uprate *faster Test Procedure IP-2.99-010, Revision 1, Renewed Operating License Aro. NPF-22 License Condition 2,C.(20)(C),"

dated February 28, 2011.

The Attachment to this letter provides the revised Susquehanna Steam Electric Station (SSbS) Unit 2 Extended Power Uprate (EPU) Master Test Procedure (EP-299-( 10, R.CViS [On 3).Thi.slroced.ure -was revised to incorporate editorial changes identil"ied at ALA-6697 was submitted to the NRC.

If you have any questions or require additional infor! i;lion, please contact Mr. Duane Filchner at (610) 774-7819.

I declare -l 1.(ler penal( ofperjury that the ant' . zort--z.

ecut on:

'fP-299-010, Rev.. 3, t 2 Extended Power Uprate 'est Infrequent or. Complex est/Evolution (SIC TI)

1)ocurnent Control Desk PI J1-671 5 Copy: NRC Region I Mr. P. W. Finney. NRC Sr. Resident Inspector Mr. R. R. Jaiiati, I)E1)/13RP Mr. B. K. Vaidya, NRC Project Manager

Attachment to PLA-6715 TP-299-010, Rev. 3, Unit 2 Extended Power Uprate Master Test Procedure Special, Infrequent or Complex Test/Evolution (SICT/E).

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PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC PROCEDURE EXTENDED POWER UPRATE MASTER TEST PROCEDURE TP-299-010 SPECIAL, INFREQUENT OR COMPLEX TEST/EVOLUTION Revision 3 (SICT/E) Page 1 of 71 ADHERENCE LEVEL: STEP-BY-STEP ,

QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

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

( ) Instruction EFFECTIVE DATE: 4 fa(gori PERIODIC REVIEW FREQUENCY: N/A PERIODIC REVIEW DUE DATE: N/A RECOMMENDED REVIEWS:

Operations, Reactor Engineering, Station Engineering, PORC Procedve 0.wrer:

FORM NDAP-QA-0002*1, Rev, 4, Page of (Etectronlc Form)

TP-299-010 Revision 3 Page 2 of 71 PROCEDURE RgVISION

SUMMARY

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

1) Revised to incorporate Nuclear Regulatory Affairs comments captured in ARICR 1382949:

a) Corrected power levels identified in Unit 2 License Conditions 2.C.(20)(b)(3), 2.C.(20)(b)(5) and 2.C.(20)(a)(4) from 3733 MWt to 3489 MWt.

2) Corrected reference section in step 7.3.1.

3) Above changes are administrative and do not alter Intent of procedure requiring PORC review.

TP-299-010 Revision 3 Page 3 of 71 TABLE OF CONTENTS SECTION PAGE

1. PURPOSE/SCOPE 6

2. DISCUSSION 6

3. REFERENCES

4. TEST EQUIPMENT 10

5. PRECAUTIONS/NOTES 11

6. PREREQUISITES 12

7. PROCEDURE 14 7.1 Mode 5 / Mode 4 Testing 14 7.2 Preparations for entering Mode 2 14 7.3 Startup to 83% Power and Test Condition A Testing 16 7.4 Test Condition B Testing 20 7.5 Test Condition C Testing 21 7.6 Preparation for Power Asow.i: (94.4%) 2.3 73 (Start Sinvorq Ascenido! . ;

.m\iv7 ca-te,.

TS 29 5 .9 P for Powc . 31 7..11 TS.: iZ. Tos 7.12 IC L. ) 39 7.13 TC E Testici:.3 at Maximum Allowable Core Flow 40 7 14 Test C:. : ., ndit!op 1.1; Review

TP-299-010 Revision 3 Page 4 of 71 TABLE OF CONTENTS (Cont'd)

SECTION PAGE

8. RESTORATION 42

9. ACCEPTANCE CRITERIA 42

10. REVIEW 42

11. RECORDS 43 ATTACHMENTS ATTACHMENT PAGE A Test Control Documentation 44 B EPU Test 42 - Required 18,C Surveillances 45 C Test Condition A Review Summary 46 EPU Test Condition Definitions 48 E Test Condition B Review Summary 49 F Test Condition C Review Summary T - .18 Moisture Garryco44 51' Ut..1 2 y;n 4,4kotivilies far 4, 5

'rest ,Jrnmary 5,3 54 55 ST-12r, 57 M sr-12A NST-19 Core Performance ':'esiing 59 rc.,s!. Plateau Review Record

TP-299-010 Revision 3 Page 5 of 71 ATTACHMENTS ATTACHMENT PAGE P Deleted Not used during U2-15R10 Startup 61 Q Final Test Program Review Record 62 R TP-299-010 Subtest Numbers 63 S ST-1A Chemical and Radiochemical 65 ST-10 IRM Performance 66 U ST-2 Radiation Measurements 67 ST-22 Pressure Regulator 68 W ST-24 Turbine Valve Surveillance 71

TP-299-010 Revision 3 Page 6 of 71 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 2 Phase 2 Extended Power Uprate Test Program. Specifically, this procedure provides a method of:

1.1 Ensuring that requirements for commencing testing in each Test Condition are met. (Refer to Section 2 for a definition of Test Condition.)

12 Specifying testing to be completed during each Test Condition.

1,3 Tracking status of test implementation.

1.4 Controlling escalation of Test Conditions.

2. DISCUSSIQN 2.1 This procedure does not supersede or replace any existing plant procedure, process or program.

2,2 This procedure performs no active testing. It is used as a master checklist and guide for the overall Unit 2 Phase 2 Extended Power Uprate Test Program.

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

2,4 A Test Condition (TC) is a defined range of reactor power and core flow condi:one at which tewirig u concit.itez.-., The Test Co!!.ition also inclut) 4tnilop path to thos ,7 fa$:t. C/nditiOn$ "ft 7 Phase 2 2.4.1 A- th:71 52'2 .3

• 'IC A is iiwn 2,42 IC 2.4.3 TO C - Reactor power between 3658 and 3733 Wit (92:i.PA and 94.4%) with any core flow within the safe ope'ating regio ,i of the

TP-299-010 Revision 3 Page 7 of 71 2.4.4 TC 0 - Reactor power between 3779 and 3855 MWt (95.6% and 97.5%) with any core flow within the safe operating region of the Power/Flow Map.

2.4.5 TC E Reactor power between 3873 and 3952 MWt (98.0% and 100%) with any core flow within the safe operating region of the Power/Flow Map.

2.5 A Test Plateau is an administrative grouping of one or more Test Conditions and/or plant conditions to support efficient control of test scheduling, results review and power escalation. The Test Plateaus for the Unit 2 Phase 2 EPU Test Program are as follows:

2.5.1 94.4% Power Test Plateau - Includes startup and operation up to and including 94.4% power (3733 MWt) which includes TC A, TC B, and TC C.

2.5,2 97.5% Power Test Plateau - Includes startup and operation up to and including 97.5% power (3855 MWt) which includes TC D.

2.5.3 100% Power Test Plateau - Includes startup and operation up to and including 100% power (3952 MWt) which includes TC E.

2.6 Attachments C, E, F, I and K specify the minimum tests that are required to be completed in TC A, TC B, TC C, TC 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 ono to three digit number and aivriays, present, y is en charact ,Fir and is

.firtitrary tes!!. ','-frorl t,h=,) in 2:7 a Test. Cum..;:tcH iflt;>'6 CR,1e3 method fur ensuing that all testing within each Test Condition is completed and insures that all required reviews and prerequi:=::tes are satisfied curing the from Y;. the i hr

TP-299-010 Revision 3 Page 8 of 71 2.9 Those sections of this procedure that provide direction to initially increase power beyond 3733 MWt are classified as Special, Infrequent or Complex Test/Evolutions (SICT/E's) 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.

2,10 The maximum core flow limit is 108 Mlb/hr.

3. REFERENCES 3.1 CH-SY-026, Moisture Carryover 3.2 GO-200-002, Plant Startup, Heatup, and Power Operation 3,3 GO-200-004, Plant Shutdown to Minimum Power 3.4 HP-TP-522, Radiological Survey Program in Support of the Unit 2 Extended Power Uprate Modification 3.5 NDAP-QA-0008, Procedure Writers Guide 3.6 NDAP-QA-0320, Special, Infrequent or Complex Test/Evolutions 3.7 NDAP-QA-0406, Extended Power Uprate Test Program 3.8 . NSEP-QA-0004, Station Engineering Surveillance and Technical Procedures Preparation and Performance Guidelines

,D08, Shift Tettnicl,iii At'OF.?nr Ott 'al t`r l^fbit ite Cg-TA 3.10 OP and Com f?:,::1 e *

'3.11 ".Fuel 3,12 ' . ";17.

3;13 RE-21 3.1411. * '%4 3.15 Sei-23-10 -:;?, U2 IB.',&74`. 'Aorttfil y 3.16 SC-243-101, U2 Main Conden s er Air Ejector Monthly Noble Gas 3.17 iSC-276-101 Coolant

TP-299-010 Revision 3 Page 9 of 71 3.18 SC-276-102, U2 Primary Coolant Specific Activity Dose Equivalent 1-131 3.19 SC-276-106, U2 Rx Coolant Chloride and pH Determination 3.20 SE-264-305, Recirc MG Set Positioners High Speed Stops 3,21 SE-278-001, APRM 21 Drive Flow Calibration 3.22 SE-278-002, APRM 22 Drive Flow Calibration 3.23 SE-278-003, APRM 23 Drive Flow Calibration 3.24 SE-278-004, APRM 24 Drive Flow Calibration 3.25 SI-278-301A, Semi Annual Calibration IRM Channel 2A 3.26 S1-278-301B, Semi Annual Calibration IRM Channel 2B 3.27 SI-278-301C, Semi Annual Calibration IRM Channel 2C 3.28 SI-278-301D, Semi Annual Calibration IRM Channel 2D 3.29 S1-278-301 E, Semi Annual Calibration 1RM Channel 2E 3.30 S1-278-301 F, Semi Annual Calibration IRM Channel 2F 3.31 SI-278-301G, Semi Annual Calibration IRM Channel 2G 3,32 Si 278'301H, Semi Annual Calibration iRM Channel 2H

.433 Wit; . .

qqty f:;;;

337 Si-283-307, 24 Month Gaiib;aVon of Main Steam Line C How Channels FiS-B21-2N009A&A and Main Steam Line D Flow Channels FIS-B21-2N009A&B 138 SO -2 Cry?..i..ming Log

TP-299-010 Revision 3 Page 10 of 71 3.39 SO-278-004, Weekly APRM Calibration 3.40 SR-200-008, In Sequence Critical and Shutdown Margin Demo 3.41 SR-255-004, Scram Time Measurements of Control Rods 3.42 SR-278-012, LPRM Calibration Validation 3,43 TP-055-001, CRD Stroke Time and Friction Measurement 3.44 TP-200-013, EPU Data Collection and Extrapolation 3.45 TP-245-029, Feedwater Master Water Level Controller MWLC Tuneup (SICT/E) 3.46 TP-262-033, Steam Dryer Vibration Testing 3.47 TP-264-032, Core Flow Calibration 3.48 TP-293-041, EPU EHC Pressure Regulator Testing 3.49 TP-299-011, Cooling Water Systems Start-Up Test for EPU 3.50 EC 690276, EPU Implementation Engineering Change Unit 2 3.51 EC-PUPC-2070, EPU Flow Induced Vibration Testing and Walkdown Criteria 3.52 EC-PUPC-2097, Revised Susquehanna Replacement Steam Dryer Limit Curves Main Steam Line Mounted Instrumentation 3,53 M1156:., ir Engineering Sper.,%;, hx.encied Power Lip.rate Startup est vit,1 3:54

3SES 1)-

4. TEST EQUIPMENT No 3 .:; ; fit; &Iva: y re.:*14'..)!-

TP-299-010 Revision 3 Page 11 of 71 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. Not all Startup Tests have a specific procedure that covers the required testing. Some startup test requirements require multiple procedures to capture all required testing and acceptance criteria. Existing procedures are utilized where possible with specific acceptance criteria unique to the Startup Test Program captured in the form of attachments to this procedure.

5.3 Per Unit 2 Operating License Condition 2.C. (20) (d), the following key attributes of the PATP (Power Ascension Test Program) shall not be made less restrictive without prior NRC approval.

5.3.1 During initial power ascension testing above 3489 MWt, each test plateau increment shall be approximately 3.5% of 3489 MWt (122 MWt);

5.3.2 Level 1 performance criteria; and 5.3.3 The methodology for establishing the stress criteria used for the Level 1 and Level 2 performance criteria Changes to other aspects of the PATP may be made in accordance with the guidance of Nuclear Energy Institute (NEI) 99.04, "Guidelines for Managing NRC Commitments," issued 5..4 Per. Unit i Condition 2: .:, 1,0 3, .'"FiPt. holt . the at e .. Ch 3.5Yr, :step to isti:

• 17' acceptance -,titerlor exceed (..c.: shat; rksy.repa:

document the continr..od structural inte g rity of the steam dryer and provide that documentaton to the NRC Staff by facsimile or electronic transmission to the Ntio.0 prcient manager prior to furrner

TP-299-010 Revision 3 Page 12 of 71 5.6 Per Unit 2 Operating License Condition 2.0 (20) (a) 5, In addition to evaluating the dryer strain and MSL, strain gauge data, PPL shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers during power ascension above 3489 MWt. - If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, PPL shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power."

6. PREREQUISITES 0 6.1 A SICT/E Analysis, Form NDAP-QA-0320-1, has been completed by the Test Director/Evolution Coordinator and attached to this procedure prior to procedure implementation.

Confirmed By Date 0 6.2 Partial Closure 1 and 2 of EC 690276, Extended Power Uprate Implementation, are closed.

Confirmed By Date 6.3 Administrative Hold Condition for restricting entry into Mode 2 has been initiated as follows:

4 uir.irrned

TP-299-010 Revision 3 Page 13 of 71 6.4 Administrative Hold Condition for reactor power not to exceed 3733 MWt (94.4%)

has been initiated as follows:

0 6.4.1 ZWO document specifying Administrative Hold Condition has been issued.

ZWO number:

6.4.2 Unit 2 Shift Supervision has been informed of Administrative Hold Condition and to include the hold condition in the Unit Supervisor Turnover Sheet.

6.4.3 Work Week Management has been informed to add the Administrative Hold Condition and associated ZWO number as a Log Line to the appropriate activity in the station schedule.

Confirmed By Date 6.5 Administrative Hold Condition for reactor power not to exceed 3855 MWt (97.5%)

has been initiated as follows:

0 6.5.1 ZWO document specifying Administrative Hold Condition has been issued.

ZWO number:

6.5.2 Unit 2 Shift Supervision has been informed of Administrative Hold

. e nd to include the hold condition in the Unit Supervisor Sheet,

. , . tr:7: :ad(i

&g

TP-299-010 Revision 3 Page 14 of 71

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

NOTE (2): Tests identified in an attachment may be completed in any order unless otherwise specified.

7.1 Mode 5 / Mode 4 Testing 0 7.1.1 Confirm that Shift Supervision Is aware that testing identified in Attachment C, Test Condition A Review Summary for Mode 5 or Mode 4 may commence.

Confirmed By Date (Shift Supervision) 7.1.2 Perform tests listed in Attachment C, Test Condition A Review Summary that that are specified for Mode 5 and Mode 4.

7.2 Preparations for entering Mode 2 NOTE: Steps 7.2.1 through 7.2,3 may be completed in any order.

7,2.1 Confirm the following:

NOTE ST to in Model pti,t7, r to , =k a5 pow-3, lest Results Summaries for carnpeted Tests listed in Attachment C have been reviewed by the Tp-299-010 Test DLrec,:tor or EPU Test Program M-ector.

TP-299-010 Revision 3 Page 15 of 71 0 c. Test Exception Reports have been written for any test listed in Attachment A that was not successfully completed.

d. Ail Test Exception Reports, if any, have been dispositioned.

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

Confirmed By Date (EPU Test Prog Director) 7.2.2 Confirm that all items in GO-200-002 Attachment A "Unit 2 Station Verification of Activities for Entering Mode 2" have been signed off.

Confirmed By Date (Shift Supervision) 7.2.3 Obtain permission from the Plant Manager to perform following:

a. Enter Mode 2.

b. Increase reactor thermal power with plant conditions not to exceed 3733 MWt (94.4%) or 108 Mlbm/Hr core flow.

0. Perform all remaining tests listed in Attachment C, Test

-qion A Re ,41.-. `-'31_11-fmary.

F., Ctt rC

/

rqaT 4: !9PT1S41'.'e 7

Close ZWO issued in prerequisite 6 3,

TP-299-010 Revision 3 Page 16 of 71 O b. Remove Administrative Hold Condition from the Unit Supervisor Turnover Sheet, Confirmed By Date (Shift Supervision) 7.3 Startup to 83% Power and Test Condition A Testing 7.3.1 Confirm Shift Supervision is cognizant of the Administrative Hold Condition that Reactor power may not exceed 3733 MWt (94.4%)

initiated in prerequisite 6.4 until this Administrative Hold Condition is lifted by this Test Procedure or as otherwise notified by the Plant Manager. Reactor thermal power may briefly exceed 3733 MWt during minor power transients inherent to approved test procedures.

1 Confirmed By Date 7.3.2 Confirm that Shift Supervision is aware that all tests listed in Attachment C, Test Condition A Review Summary, can be performed in any order at reactor power levels not to exceed 3302 MWt (83.3%) or at lower power levels as specified in Attachment C. Reactor thermal power may briefly exceed 3302 MWt during minor power transients inherent to approved test procedures.

,*.ri Date Rf:tg *:3"t1C.:0.7 COW , 22,:"

Sync. This data should he ..:ailected at inter ,iats not to excend (of .scaie) reactor power..

TP-299-010 Revision 3 Page 17 of 71 NOTE: if Reactor Power is ever reduced below 16%, AND the Reactor Mode is changed from Mode 1 to Mode 2, THEN ST-10.2 IRM/APRM overlap is required to be performed. This overlap check is only valid if an APRM calibration was performed while in Mode 1 prior to entering Mode 2. ST 10,2 is satisfied by performance of GO-200-004, following removal of Main Generator and shutdown of Main Turbine.

7.3.6 Perform ST-22.2, Scram Bypass Setpoint Verification (TP-293-041), during power ascension. This should occur prior to exceeding 26% power (1027MWt) 0 7.3.7 Continue power ascension AND Complete ST 5.2, Control Rod Scram Time Measurement (SR-255-004) for any required remaining control rods not previously tested prior to exceeding 40% power (1580 MWt).

7.3.8 Continue power ascension to 60% power.

7.3.9 Perform 60% Pressure Regulator testing.

0 a. Complete TP-299-010 Attachment V, ST-22 Pressure Regulator, to satisfy requirements for monitoring Pressure Regulator Incremental Regulation performance up to and including 60% power.

Perform ST-22.2, Pressure Regulator Step Changes and Pressure Regulator Failure in accordance with TP-293-041 complete V, 57'r 22 k :

• rt.;"":!..if'e Regulator', !-;, pressure icig ,

respn 7.3,10 sting acpci,.,*;;,::,e 2.77 1'404if It;

t. Record two 3 minute segment datasets of MSL Strain Gauges.

TP-299-010 Revision 3 Page 18 of 71 El c. AFTER the MSL Strain Gauge datasets are recorded, Evaluate the measured data to ensure the instrumentation is operating properly. Correct and repeat the data recording if necessary.

d. Record reactor operating conditions at the time MSL data is recorded by completing PI data sheet.

e. Inform Operations that the tolerance of +/- 12 MWt on reactor power is no longer in effect f Evaluate dataset AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date (EPU Engineering) 7.3.12 Inform Operations that vibration test results are acceptable and that reactor power level may be increased per station schedule to 83.3% (3293 MWt) t .25% (3283 3302 MWt).

7.3.13 Continue power ascension to approximately 83.3% power.

7.3.14 Perform remaining tests listed in Attachment C, Test Condition A Review Summary.

7.3.15 Perform following 83.3% vibration testing in accordance with TP-262 07' eadDir Li,r.

b.

(3) Record reactor operaOlci conditions at the time MSL data !,s recorded by completing PI data sheet.

Rf::!coro

TP-299-010 Revision 3 Page 19 of 71

d. Record a dataset of Recirculation and RHR accelerometers.

a. Record a dataset of vibrations as required to be taken With Local Vibration Monitoring instrumentation.

Perform walkdown of accessible areas.

g. Perform walkdown of inaccessible areas

h. Inform Operations that the minimum power level of 3283 MWt is no longer in effect.

Evaluate datasets AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date (EPU Engineering) 7.3.16 Confirm the following:

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

All EPU Test Results Summaries for completed Startup Tests listed in Attachment C have been reviewed by the TP-299-010 Test ['I -ector or EPU Test Program Director.

C.

TP*299-010 Revision 3 Page 20 of 71 7.4 Test Condition B Testing 7.4 .1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition B in Attachment D EPU Test Condition Definitions.

7.4.2 Confirm that Shift Supervision is aware that all tests listed in Attachment E, Test Condition B Review Summary, can be performed in any order at reactor power levels In the range of 3293 to 3360 MWt (83.3% to 85.0%). Reactor thermal power may briefly exceed 3360 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date (Shift Supervision) 7.4.3 Perform tests listed in Attachment E Test Condition B Review Summary.

7.4.4 Confirm the following;

a. All testing listed in Attachment E, Test Condition B Review Summary, has been successfully completed QB Test Exception Reports have been written.

b. All EPU Test Results Summaries for completed Startup Tests listed in Attachment E have been reviewed by the

". 2 299 , 1.10

- r recto:- or FPU "rest Program Director.

0 k-B' ports ^ " Sid.

TP-299-010 Revision 3 Page 21 of 71 7.5 Test Condition C Testing 7.5.1 Inform Shift Supervision to Establish reactor conditions within those defined as EPU Test Condition C in Attachment ID, EPU Test Condition Definitions.

CI 7.5.2 Confirm that Shift Supervision is aware that all tests listed in Attachment F, Test Condition C Review Summary, can be performed in any order at reactor power levels in the range of 3658 to 3733 MWt (92.6% to 94A%) as specified in Attachment F.

Reactor thermal power may briefly exceed 3733 MWt during minor power transients inherent to approved test procedures.

Confirmed By Date (Shift Supervision)

CAUTION RPV Level Instrumentation or MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are identified as Increasing above.nominal levels in proportion to instrumentation data, power ascension shall be stopped and the Issue evaluated and conveyed to the NRC prior to further power ascension. (Excerpt from Operating License Condition 2.0 (20)(a) 5).

7.5.3 Perform following 94.4% vibration testing in accordance with TP-262-033!

a Maintan power ' MVVI dateset rwtre segment datax,ets of MSL (3) Record .,peating cond!Uons it7i Vrte MSt. data is recorded by completiNg pi data sheet:

El c. Record

TP-299-010 Revision 3 Page 22 of 71

d. Record a dataset of Recirculation and RHR accelerometers.

e. Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.

Perform Walkdown of accessible areas.

g. Perform Remote Walkdown of inaccessible areas.

h. Inform Operations that the minimum power level of 3715 MWt is no longer in effect.

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

Confirmed By Date (EPU Engineering) 7.5.4 LPRM Calibration ST 11

a. Request Reactor Engineering to determine if an LPRM Calibration is required during Test Condition C.

b, IF yes, THEN Perform ST 11 as listed in Attachment F (SR-278-012).

iF_ not aquired, THEN Document jt,t ,..tification for rmt perr; 11 i Test Repixt

.-ept.v.11 listed in Attachment E that was not successfully ,

• mpleted

TP-299-010 Revision 3 Page 23 of 71 0 d. All Test Exception Reports have been dispositioned.

Confirmed By Date (EPU Test Prog Director) 7,5.7 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval.

7.6 Preparation for Power Ascension Above 3733 MWt (94.4%)

NOTE: Steps 7.6.1 through 7,6.8 may be completed in any order.

7.6.1 Confirm that all CRs and CRAs necessary for power ascension above 3733 MWt (94.4%) up to a maximum of 3855 MWt (97.5%)

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

Confirmed By Date Supervisor-Corrective Action and Assessment 7.6.2 Confirm the following:

a, There are no open Test Exceptions or Correct Condition red to Exceptions r, =cured to c, tlt,)OVEt b.

TP-299-010 Revision 3 Page 24 of 71 7.6.3 Confirm Test Plateau Review Record for the 94.4% Plateau has been approved by TRC, PORC and Plant Manager with recommendation and approval to continue power ascension to the next plateau as documented on Attachment O.

Confirmed By Date 0 7.6.4 , Complete Attachment Unit 2 Station Verification of Activities for power ascension.

0 7.6.5 Confirm that Reactor Engineering is aware that the initial power increase from 3733 MWt to 3855 MWt shall be made using recirculation flow along a constant rod line at an average power ascension rate not to exceed 1 %/hr.

Confirmed By Date (Reactor Engineering)'

7.6,6 Obtain permission from the Plant Manager to perform following:

a. Increase reactor thermal power with plant conditions not to exceed 3855 MWt (97.5%) or 108 Mlbm/Hr core flow.

b. Perform all tests listed in Attachment I, Test Condition D Review Summary.

Piant Manager

TP-299-010 Revision 3 Page 25 of 71 7.7 (Start of SICT/E Section) Initial Power Ascension Above 3733 MWt (94.4%).

NOTE (1): The initial power ascension above 3733 MWt will be from 3733 MWt (94.4%) to 3855 MWt (97.5%) using recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr.

NOTE (2): BOP parameters such as main generator gross electrical output and main condenser pressure may limit reactor thermal power to a level less than 3855 MWt (97.5%).

NOTE (3): if 3855 MWt is not achieved during the initial power ascension above 3733 MWt, subsequent power ascensions above the previous maximum power level achieved may be desired and are permissible.

NOTE (4): Subsequent- power ascensions above previous maximum power levels attained shall be done using reactor recirculation flow along

• a constant rod line at an average power ascension rate not to exceed 1%/hr. It is not necessary to use the same rod line that was used in the initial or subsequent previous power ascensions.

NOTE (5): All testing performed during Test Condition D must be done within the range of 3779 MWt to 3855 MWt (95.6% to 97.5%) or at lower power levels as specified in Attachment 1. Reactor thermal power may briefly exceed 3855 MWt during minor transients inherent to approved test procedures.

"7 (6): in the event acQ.distiosignah that 0 ;,.11-tr1;7, curve drifer h it be $net

• ACM ac.)L' treLitie!:)C:y t:NJ f:;e',rfOrtntid. (Excerp Loense 77.1 Complete the Specai, infrequent, or Complex TestiEvci!JtV1 (SICT/E) briefing us:ng Form NDAP-QA-0320-2 ANO Attach the folioWng completed forms to this procedure:

a .SICT/E rorm

TP-299-010 Revision 3 Page 26 of 71

b. SICTIE Roster, Form NDAP-QA-320-3 Confirmed By Date (Designated Activity Manager) 7.7.2 Inform Unit 2 Shift Supervision that the Administrative Hold Condition for exceeding 3733 MWt (prerequisite 6.4) has been lifted AND to Perform following:

0 a. Close ZWO issued In prerequisite 6.4.

b. Remove the Administrative Hold Condition from Unit Supervisor Turnover Sheet.

Confirmed By Date (Shift Supervision) 7.7.3 Confirm Shift Supervision is cognizant of the Administrative Hold Condition that Reactor power may not exceed 3855 MWt (97.5%)

until this Administrative Hold Condition is lifted by this TP or as otherwise notified by the Plant Manager. Reactor thermal power may briefly exceed 3855 MWt during minor power transients inherent to approved test procedures.

Confirmed By 7,T4. ti r r 1.5; q.;.tt It teztig in of 37Th to 97,...r' 1 ai AsAg..f:3, as

TP-299-010 Revision 3 Page 27 of 71 7.7.5 Confirm required reactivity briefing and controls have been completed in accordance with OP-AD-338 to support the power ramp. Note that completion of this step may be performed out of sequence with this section.

Confirmed By Date (Shift Supervision)

CAUTION (1)

If any frequency peaks from MSL Strain Gauge data exceed limit curves above 3489 MWt, Reactor Power shall be returned to a power level at which the acceptance criteria is not exceeded. (Excerpt from Operating License Condition 2.C.(20) (a) 4).

CAUTION (2)

RPV Level Instrumentation or MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, power ascension shall be stopped and the issue evaluated and conveyed to the NRC prior to further power ascension. (Excerpt from Operating License Condition 2.C(20)(a) 5).

L 7.7.6 Inform Test Director for TP-252-033, Steam Dryer and Flow Induced Vibration Testing that the initial power ascension from 3733 MWt (94.4%) to 3855 MWt (97.5%) is about to commence AND Confirm that all test personnel are in place and prepared to perform assigned duties f

TP-299-010 Revision 3 Page 28 of 71 NOTE: All thermal power ascension ramps above previously attained thermal power levels must meet the following requirements:

• SICT/E Controls must be established in accordance with N DAP-QA-0320

• TP-262-033 and 0I-TA-008 test personnel must be in place and ready to monitor and record data

• Power ascension ramps are limited to less than or equal to 1% / hour

• Power ascension ramps are to utilize Reactor Recirculation flow only Vibration datasets during power increases are collected but not analyzed and inserted into the Test Point Report. Datasets are analyzed at each 3.5% plateau. (Excerpt from Operating License Condition 2.C(20)(a) 3).

7.7.7 Complete ramp to 3855 MWt (97.5%) as follows:

a. Complete Attachment J, EPU Test Program Power Ramp Data, items recorded prior to start of ramp step.

0 b. Inform Shift Supervision to perform a power increase step not to exceed 1% per hour increase in reactor power.

c. Complete Attachment J items recorded for the power r rid step:

the power 262-033 Record a t."

laiKeo with -

ii-,(3((,- u.m * (

` Record of rviliSL, ar: Is7'2V 0 ( 5) Record a dataset of Recirculation and RHR adde.lerometers,

() Record a dic4;:i(Fir.iitt

TP-299-010 Revision 3 Page 29 of 71 0 (7) Perform Walkdown of accessible areas.

0 (8) Perform Remote Walkdown of inaccessible areas.

0 e. Repeat Steps 7.7.7.a d above when directed by Reactor Engineering until 3855 MWt is achieved.

NOTE: After the plant has reached a stable steady state power level of 3855 MWT (97.5%) the SICT/E for this plateau is terminated.

7.8 Test Condition D Testing 7.8.1 Perform testing listed in Attachment I, Test Condition Review Summary, while completing the remaining steps In this section.

7.8.2 Perform following 97.5% vibration testing in accordance with TP-262.033:

0 a. Maintain reactor power between 3837 MWt and 3855 MWt (97% - 97.5%) as displayed on PICSY point NBA01.

b. Perform MSL Strain Gauge dataset recordings:

(1) Record two 3-minute segment datasets of MSL Strain Gauges.

(2) AFTER the are rer.. - velc1(;,

4.

f. Perform Walkdown of ac,cessib!ic:

Perforn)

TP-299-010 Revision 3 Page 30 of 71

h. Inform Operations that the minimum power level of 3837 MWt is no longer in effect.

0 i. Evaluate datasets AND Confirm that results are within the Level 1 and Level 2 Acceptance Criteria.

Confirmed By Date (EPU Engineering) 7.8,3 Prepare a steam dryer performance evaluation for 3855 MWt as required by License Condition 2.C.(20)(a)3.

7.8.4 Record following date and time information:

a. Performance Evaluation submitted to the NRC Project Manager.

Date Time 0 b. NRC Project Manager confirms receipt of transmission.

Date Time Cnnfirrned By Date 7.8.5 . Confirrrg c.

cornp -7 0

0  ; red.

C orf By Dat

'Test Proq Director)

TP-299-010 Revision 3 Page 31 of 71 0 7.8.6 Prepare a Test Plateau Review Record, Attachment 0, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval.

7.9 Preparation for Power Ascension Above 3855 MWt (97.5%)

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

0 7.9.1 Confirm that all CRs and CRAs necessary for power ascension above 3855 MWt (97.5%) are resolved and Responsible Supervisor certifies that all required work is completed.

Confirmed By Date Manager-Corrective Action and Assessment 7.9.2 Confirm that at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> have elapsed since the NRC Project Manager confirmed receipt of the steam dryer performance evaluation for 3855 MWt as required by License Condition 2.C.(20)(a)3.

0 a. Date and time that NRC Project Manager confirmed receipt of information (from step 7.8.4.b) Date Time

b. Line a plus 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, Date

1. Da t9 Date Titre t.t.i;1!e .elaoseci ,`P!ti o b)

Coofirtrt be C 0 m pi ete d and closed prior to noreasing power above 3855 MWt (97.5%),

TP-299-010 Revision 3 Page 32 of 71 0 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 (CPU Test Prog Director) 7.9.4 Confirm Test Plateau Review Record for the 97.5% Plateau has been approved by TRC, PORC and Plant Manager with recommendation and approval to continue power ascension to the next plateau as documented on Attachment 0.

Confirmed By Date 0 7.9.5 Complete Attachment H, Unit 2 Station Verification of Activities for Power Ascension.

7.9.6 Confirm that Reactor Engineering is aware that the initial power increase from 3855 MWt to 3952 MWt shall be made using recirculation flow along a constant rod line at an average rate not to exceed 1%/hr.

C onfirmed By Date (Reactor Engineering)

Obtain frOfn the. PN.(it Manager to no 'to in k E

TP-299-010 Revision 3 Page 33 of 71 7.10 (Start of SICTIE Section) initial Power Ascension Above 3855 MWt (97.5%).

NOTE (1): The initial power ascension above 3855 MWt will be from 3855 MWt (97.5%) to 3952 MWt (100%) using recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr.

NOTE (2): BOP parameters such as main generator gross electrical output and main condenser pressure may limit reactor thermal power to a level less than 3952 MWt (100%).

NOTE (3): If 3952 MWt is not achieved during the initial power ascension above 3855 MWt, subsequent power ascensions above the previous maximum power achieved may be desired and are permissible.

NOTE (4): Subsequent power ascensions above previous maximum power levels attained shall be done using reactor recirculation flow along a constant rod line at an average power ascension rate not to exceed 1%/hr. It is not necessary to use the same rod line that was used in the initial or subsequent previous power ascensions.

NOTE (5): All testing performed during Test Condition E must be done within the range of 3873 MWt to 3952 MWt (98.0%© to 100%) or at lower power levels as specified in Attachment K.

N (G): in the eve, ait,ohstto sigrak are identified ttla-l: the curvi;,) hnq power ef.cert..i3irir loads

;;.,j $ certbrrrit. (Excerst. from NKITE cry

. filtiNt.,

7,10.1 Complete .tie 6per.:iai, Infrequent, or Complex Test/E-i..oli.itic:in (SICT/E) briefing using Form NDAP-QA-C320-2 AND Attach the foliov., ng completed forms to this procedure:

11,, Form ND.Ap-CA-32.0-2

TP-299-010 Revision 3 Page 34 of 71 0 b. SICT/E Roster, Form NDAP-QA-320-3 Confirmed By Date (Designated Activity Manager) 7.10.2 Inform Unit 1 Shift Supervision that the Administrative Hold Condition for exceeding 3855 MWt (Prerequisite 6.5) has been lifted AND to Perform following; 0 a. Close ZWO issued in Prerequisite 6.5.

0 b. Remove the Administrative Hold Condition from Unit Supervisor Turnover Sheet.

Confirmed By Date (Shift Supervision) 0 7.10.3 Confirm that Shift Supervision is aware that all tests listed in Attachment K, Test Condition E Review Summary, can be performed in any order at reactor power levels in the range of 3873 to 3952 MWt (98.0% to 100%) or at lower power levels as specified in Attachment K.

Confirmed By Date (Shift Supervision)

TP-299-01 0 Revision 3 Page 35 of 71 CAUTION (11 If any frequency peaks from MSL Strain Gauge data exceed limit curves above 3489 MWt, Reactor Power shall be returned to a power level at which the acceptance criteria is not exceeded. (Excerpt from Operating License Condition 2.0 (20) (a) 4).

CAUTION (21 RPV Level Instrumentation or MSL Piping accelerometers shall be monitored during power ascension above 3489 MWt. If resonance frequencies are Identified as increasing above nominal levels In proportion to instrumentation data, power ascension shall be stopped and the issue evaluated and conveyed to the NRC prior to further power ascension. (Excerpt from Operating License Condition 2.0 (20) (a) 5).

7.10.4 Inform Test Director for TP-262-033, Steam Dryer and Flow Induced Vibration Testing that the initial power ascension from 3855 MWt (97,5%) to 3952 MWt (100%) is about to commence An Confirm that all test personnel are in place and prepared to perform assigned duties.

Confirmed By Date 7.10.5 Confirm required reactivity briefing and controls have been completed in accordance with OP-AD-338 to support the power ramp. Note that completion of this step may be performed out of sequence with this section.

Cott riled Evy SupervGion)

TP-299-010 Revision 3 Page 36 of 71 NOTE: All thermal power ascension ramps above previously attained thermal power levels must meet the following requirements:

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

• TP-262-033 and 0I-TA-008 test personnel must be in place and ready to monitor and record data

• Power ascension ramps are limited to less than or equal to 1% / hour

• Power ascension ramps are to utilize Reactor Recirculation flow only Vibration datasets during power increases are collected but not analyzed and inserted Into the Test Point Report. Datasets are analyzed at each 3.5% plateau. (Excerpt from Operating License Condition 2,C(20)(a) 3).

7.10.6 Complete ramp to 3952 MWt (100%) as follows:

o a. Complete Attachment J, EPU Test Program Power Ramp Data, 'items recorded prior to start of ramp step.

Inform Shift Supervision to perform a power increase step not to exceed 1% per hour increase in reactor power.

0 o, Complete Attachment J items recorded .for the power zter4

'53 Test Drers:h2 t .. 3 perform oliving (in Alt Record (2) ( 7 ol.i*

• dat c- -4 fecorde.o ouripletos data sheet

(.41) Record a dataset of MK. and FIN accelerometers.

TP-299-01 tl Revision 3 Page 37 of 71 (5) Record a dataset of Recirculation and RHR accelerometers.

(6) Record a dataset for Ol-TA-008 Data Acquisition.

(7) Perform Walkdown of accessible areas.

(8) Perform Remote Walkdown of inaccessible areas.

e. Repeat steps 7.10.8.a d above when directed by Reactor Engineering until one of the following occurs:

(1) 3952 MWt is achieved (2) i3OP parameters such as main generator gross electrical output and main condenser pressure limit(s) are reached.

Record date and time when 3872 MWt (98.0%) was initially, achieved.

Date Time Record date and time when 3952 MWt (100%) la highest power level was initially achieved.

VOA Date

't ' 1 1, , .1

TP-299-010 Revision 3 Page 38 of 71 7.11 Test Condition E Testing NOTE: TC E is defined as 3873 MWt to 3952 MWt (98% -100%). If 3952 MINI is not achievable, required testing specified to be performed at 3952 MWt is to be performed in the band between highest power level achievable minus 18 MWt. Testing not identified to be performed at a specific power level can be performed in any order and within 3873 MWt to 3952 MWt as identified on Attachment K.

7.11.1 Perform following 100% vibration testing in accordance with TP-262-033:

0 a. Maintain reactor power between 3934 MWt and 3952 MWt (99.5% -100%) OR highest achievable power minus 18 MWt as displayed on PICSY point NBA01.

b. IF initial 100% power level was achieved with core flow between 100 Mlb/Hr and 101 Mlbm/Hr DM Maintain core flow between 100 Mlbm/Hr and 101 Mlbm/Hr.

Otherwise this step is N/A.

c. Perform MSL Strain Gauge dataset recordings:

(1) Record two 3 minute segment datasets of MSL Strain Gauges.

(2) AFTER the datasets are recorded, Evaluate the dot;:i suretlrk int3c-.1 .:, tatfori atf.0 ts data Recofd :reactor co; Th-r..:::16, at the ti.tme

d. be taice:',.

1:3 Record -

Eqici

,acoolerorrieteF$

Perform Waikdown of accessible areas, Perform Remote Walkdowr

TP-299-010 Revision 3 Page 39 of 71 0 i. Inform Operations that the minimum power level of 3934 (or highest achievable power minus 18 MWt) is no longer in effect.

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

Confirmed By Date (EPU Engineering) 7.11.2 Perform remaining testing identified on Attachment K, Test Condition E Review Summary not requiring specific core flow or power level.

NOTE: Sections 7.12 and 7.13 can be performed in either order.

7.12 TC E Testing at 100 Mib/Hr Core Flow NOTE: If core flow was established between 100 Mibm/Hr and 101 Mlbm/Hr supporting section 7.11 vibration testing, then section 7.12 can be N/A'd with documentation as to why this section is not applicable on Attachment A, Test Documentation_

7.12.1 Establish core flow between 100 and 101 Mibm/Hr (100.5 +/- .5 Mihrn/Hr).

r. 2.2 *OP.O.Wing 100 Vt./r ir 1 In accorda.qw with Tr.

,. Main. 7r1 cnre flow betweo': 100 ard .10b1Hr until ail n datast.; ha f

operating properly. Co rent ard repeat the data recording if necessary.

(3/ Record rea4":tor cperltfrVj :7; ,:::nelitiOrq-,,, ,

dea recofc,ed cdpiNetinci rjat. :r et.

TP-299-010 Revision 3 Page 40 of 71

c. Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.

d. Record a dataset of MSL, FW, Recirc and RHR accelerometers, 0 e. Inform Operations that the restrictions on core flow is no longer in effect.

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

Confirmed By Date (EPU Engineering) 7.12.3 Perform ST-1B, Moisture Carryover, by completing Attachment G, Moisture Carryover Support Data.

7.13 TC E Testing at Maximum Allowable Core Flow 7.13.1 Establish core flow between 107 Mlb/Hr and 108 Mlb/Hr.

7.13.2 Perform following 108 Mlb/Hr vibration testing in accordance with TP-262-033:

0 a, Maintain core flow between the limits established in step 7 13.1 until all vibration datasets have been con ,,:;t-ted, St min Ciatt.$;:m datwet ,rincc,xcliag' (1) Record two 3-MP .,:Aeyne:tnttfatasaig t-A4r1 (2)a Fri:4i !noonled, the

c. Record a dataset of vibrations as required to be taken with Local Vibration Monitoring Instrumentation.

TP-299-010 Revision 3 Page 41 of 71 0 d. Record a dataset of MSL, FW, Recirc and RHR accelerometers.

e. Inform Operations that the restrictions on core flow are no longer in effect.

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

Confirmed By Date (EPU Engineering) 7.13.3 Perform ST-1B, Moisture Carryover, by completing Attachment G, Moisture Carryover Support Data.

7.14 Test Condition E Review 7.14.1 Confirm the following:

a. Ali testing listed in Attachment K has been successfully completed OR Test Exception Reports have been written.

b. All EPU Test Results Summaries for completed Startup Tests listed in Attachment K have been reviewed by the TP-299-010 Test Director or EPU Test Program Director.

c. Test Exception Reports have been written for any test listed in Attachment K that was not Si4ccessfuly (lempleted.

AA 'refit Reports :have bee

e. , Date

,.r c; em s P..,ra - ari 0, '1 the C.)

!ed By Date 7 14.3 Prepare a steam dryer performance evaluation for 3952 MkAft as required by license Condition 2,C.(20)(a)3.

TP-299-010 Revision 3 Page 42 of 71 7,14.4 Record date that the steam dryer performance evaluation for 3952 MWt was provided to the NRC Project Manager, Date Confirmed By Date RESTORATION.

81 Confirm Test Plateau Review Record for the 100% Plateau has been approved by TRC, PORC and Plant Manager as documented on Attachment 0.

Confirmed By Date 8.2 Prepare a Final Test Program Review Record, Attachment Q, to the extent practical for submittal to the TRC, PORC and Plant Manager for review and approval 8.3 Confirm the final Test Program Review has been approved.

Confirmed By Date (EPU Test Prog Director)

E P TA N C E CRITERIA There are no specific Acceptance Criteria associated with this test.

tJ, a ... m*duro has bwro arid fotinci to be " P0,

,eet, te '

TP-299-010 Revision 3 Page 43 of 71

11. RECORDS 11.1 The original completed test procedure shall be transmitted to DCS.

11.2 The completed test procedure includes the attached forms identified below as well as procedure attachments:

11.2.1 SICT/E Analysis, Form NDAP-QA-0320-1 11.2.2 SICT/E Briefing, Form NDAP-QA-0320-2 11,2.3 SICT/E Roster, Form NDAP-QA-0320-3 Confirmed By Date

Attachment A TP-299-010 Revision 3 Page 44 of 71 TEST CONTROL DOCLIMENTATION Procedure No. TP-2 -0 0 Page of

Attachment B TP-299-010 Revision 3 Page 45 of 71 EPU Test 42 Rectuired Surveillances Confirm that the following procedures have been successfully completed:

SI-283-304, 24 Month Calibration of Main Steam Line A Flow Channels FIS-B21-2N006A&B and Main Steam Line B Flow Channels FIS-B21-2N007A&B 1041810

.1.1amono.

SI-283-305, 24 Month Calibration of Main Steam Line A Flow Channels F1S-B21-2N006C&D and Main Steam Line B Flow Channels FIS-B21-2N007C&D 1145886 SI-283-306, 24 Month Calibration of Main Steam Line C Flow Channels PIS-B21-2N008C&D and Main Steam Line D Flow Channels FIS-B21-2N009C&D 1179830 51-283-307, 24 Month Calibration of Main Steam Line C Flow Channels' HS-B21-2N008A&B and Main Steam Line D Flow Channels FIS-B21-2N009A&B 1075060 Confirmed By Dat.;

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AttaChment D TP-299-010 Revision 3 Page 48 of 71 EPU Test Condition Definitions (Phase 2)

Test Condition Power Level (%) Power Level (MWQ Core Flow A 0 94.4 % < 3733 MWt Note 1 B 83.3% - 85% 3293 3360 MWt Note 1 C 92.6% - 94.4% 3658 3733 MWt Note 1 D 95.6% - 97.5% 3779 3855 MWt Note 1 97.5% - 100% 3873 3952 MWt Note 1 NOTE (1): Any flow within the safe operating region of the Power/Flow Map that will produce the required power level.

NOTE (2): Test Condition definitions from EPU Startup Specification M-1563. Note that Test Condition A overlaps Test Condition A, B & C.

NOTE (3): Refer to Unit 2 approved Cycle 16 Power/Flow Map for pictorial view of test conditions.

PkPRIl,4 Calibra tion Pressure Regulator Increm entalR N

(ct, N N

legion & Extrapolation E 0

0 Moisture Carryover E

L. PRMCalibration APRM Ca libration cc 0

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Attachment G TP-299-010 Revision 3 Page 51 of 71 ST 1B Moisture Carryover Testing Test Condition Core Flow Completion of the following steps satisfies the requirement of ST 1B:

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

2. Attach copy of Core Performance Verification Printouts created during performance of ST-19 at same power/flow conditions,

3. Record plant data listed in table below using specified PICSY points.

4. Inform TP-299-010 Test Director when sample has been collected.

5. Record Main Steam Line moisture content:

6. Confirm Main Steam Line moisture content is not in excess of 0,1 wt% (Level 2 Acceptance Criterion)

Confirmed By Date Parameter P3CSY Point Value Reactor Water Level NFLO1 NFLO2 NFL 01 NEFI. )

r

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Attachment H TP-299-010 Revision 3 Page 52 of 71 Unit 2 Station Verification of Activities for Power Ascension Ail action items required for power ascension above the current maximum power level of MWt for which my group is responsible have been completed.

Manager Nuclear Operations Manager Nuclear Maintenance Supervisor Reactor Engineering Supervisor Health Physics Supervisor Chemistry A

Matrger Stebon Engfraer'ing I

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Attachment L TP-299-010 Revision 3 Page 57 of 71 STUB RBM TESTING Completion of the following steps satisfies the requirement for ST 128 testing'

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

2. Level 1 Acceptance Criterion b, test 12B. Confirm that the RBM setpoints enable at the proper power levels for EPU settings, Confirmed By Qate (Station Engineering)

Attachment M TP-299-010 Revision 3 Page 58 of 71 ST 12A APRM TESTING Completion of the following steps satisfies the requirement for ST 12A testing:

1. Confirm ST-11 LPRM Calibration (SR-278-012) has been completed at current power level.

2, Perform S0-278-004,

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.

Confirmed By Date (Station Engineering)

Attachment N TP-299-010 Revision 3 Page 59 of 71 ST 19 CORE PERFORMANCE Enter Test Condition Completion of the following steps satisfies the requirements for ST 19.

1. Obtain and Attach copy of SO-200-007, Attachment A, Item 11,

2. Level 1 Acceptance Criterion a, test 19. Confirm that core thermal limits CMPRAT, CMFLCPR and CMFDLRX are less than 1.0. Refer to SO-200-007 item 11.

3. Level 1 Acceptance Criterion b, test 19. Confirm that steady state reactor power is limited to the maximum value of the lesser of either 3952 MWt or the MELLLA Boundary as depicted on.the Power / Flow map.

4. Level 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)

Attachment 0 TP-299-010 Revision 3 Page 60 of 71 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 Teq Plateau 'Review recornr? a*oprovaV EP0 1., ,.)st* Program Director Date P

• App,:

e Date

Attachment P TP-299-010 Revision 3 Page 61 of 71 Page Intentionallyleft_Blank

Attachment Q TP-299-010 Revision 3 Page 62 of 71 FINAL TEST 0 R R VI R C List all tests scheduled for the EPU Test Program which were not completed to the extent required and the related Test Exception Reports.

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

3. List aO 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 recommendedaporovai:

EPUest Program Director Date f

IRC Mee rto:

PoRc Test .,,viproveth 43,11,e, Pap or

Attachment R TP-299.010 Revision 3 Page 63 of 71 TP-299-010 SUBTEST NUMBERS TP.299-010 Implementing M-1563 Subtest Description or Procedure Number Number Title Number 1A Chemical and Radiochemical TP-299-010 Attachment S 16 Moisture Carryover TP-299-010 Attachment G 2 2 Radiological Survey Program in Support of the HP-TP-522 Unit 2 EPU Modification 3 3 Core Fuel Pool Verification RE-081-036 4 4 In Sequence Critical and Shutdown Margin Demo. SR-200-008 5 5.1 CRD Stroke Time TP-055-001 5 5,2 Scram Time Measurements of Control Rods SR-255-004 10 10 IRM/APRM Overlap GO-200-004 11 11 LPRM Calibration SR-278-012 12 12A.1 Validation of Core Thermal Power Heat Balance RE-2TP-026 12A.2 APRM CaTmr4tic.;' TP-299-0'10.

12 12A.3 21(22)6 "3)(2<: , Caliti;Tation 1 , )p F.N3M L .

15 "1;P Ur 1 cs 22 221 Pressure Regulator incremental Regulation TP-293-041 22 22.2 Scram Bypass Setpaint Verification TP-293-041 Page 1 of 2

Attachment R TP-299-010 Revision 3 Page 64 of 71 TP 299 010 SUBTEST NUMBERS TP-299-010 Implementing M-1563 Subtest Description or Procedure Number Number Title Number 22 22.3 Pressure Regulator Step Changes and Ctrl Failures TP-293-041 22 22.4 SLRC Eval and Incremental Regulation Evaluation TP-293-041 23 23 Feedwater Master Water Level Controller Tuneup TP-245-029 24 24 Turbine Valve Surveillance TP-293-041 29 29.2 Recirc MG Set Positioners High Speed Stops SE-264-305 32 32 Drywell Cooling S0-200-007 Attachment A Item 9 33 NA (Combined into ST 100) 35 35 Core Flow Calibration TP-264-032 36 36 EPU Temperature Data Collection for Service Water TP-299-011 37 37 Gaseous Radwaste Systems TP-299-010 (Combined with ST 1A) Attachment S 42 42 I&C Surveillances TP-299-010 Attachment B 49 MSt, Rad WIN,r Adjustment  %,779-360 100 100.1 Steam .t)ryer Ste TP-262-033 100 1 Ck.3 Steam Dryer Vibe Mcn _ring During Ascension TP-262,033 1,00 1004 a a.Wakdowl TP-262-C31 "1"..1;,1 101 101 I:3:;.seicno Data CoPedon & Extriloo ltibn Page 2

Attachment S TP-299-010 Revision 3 Page 65 of 71 ST 1A CHEMICAL AND RADIOCHEMICAL.

(Includes ST 37 Gaseous Radwaste)

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

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

a. SC-276-101

b. SC-276-102

c. SC-276-106

d. SC-233-101

e. SC-233-102 f, SC-243-101

2. Inform the EPU TP 299 010 Test Director that step 1 has been completed.

3. Confirm completion of analysis for the samples collected in step 1.

4. LE a Radwaste discharge has been completed since the last power increase, THEN Confirm completion of SC-069-001. OTHERWISE, N/A this step.

Confirm that the to' Ating Levd 1 Aaeptanco tAtisfie: 4.`,Thf?rt)tA def;*i -..:A * -

i. *

• 1 Acceptance Chterfrh ,-

.,:_itiFffec.P of

• fld c,*:1,..41fortn to ourrel'.

c:i of

Attachment T TP-299-310 Revision 3 Page 66 of 71 ST-1 0 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 1840AY IRM CALIB CHANNEL A S1-278-301A is current (NIMS Activity #Z0852-01) 1277439.

2. Confirm that 184DAY 1RM CALIB CHANNEL B Si-278-301B is current (NIMS Activity #Z0851-01) 1277957.

Confirm that 184DAY IRM CALIB CHANNEL C S1-278-301C is current (NIMS Activity #Z0850-01) 1277437.

4. Confirm that 184DAY 1RM CALIB CHANNEL D S1-278-301D is current (NIMS Activity #Z0849-01) 1277956.

Confirm that 184DAY 1RM CALIB CHANNEL E S1-278-301E is current (NIMS Activity #20848-01)1 277436.

Confirm that 184DAY IRM CALIB CHANNEL F S1-278-301F is current (NIMS Activity #Z0847-01) 1277955.

7. Confirm that 184DAY IRM CALIB CHANNEL G SI-278-301G is current (NIMS Activity #20846-01) 1277954.

Confirm that 184DAY 1RM CALIB CHANNEL H S1-278-301H is current (NIMS Activity #Z0845-01) 1277950.

Cr)rIfTrinacl Page I of 1

Attachment U TP-299-010 Revision 3 Page 67 of 71 ST-2 RADIATION MEASUREMENTS Enter Test Condition Completion of the following steps satisfies the requirements for ST 2.

1. Confirm completion of HP-TP-522.

2. Confirm that the following Level 1 Acceptance Criterion is satisfied: The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of The Standard for Protection Against Radiation as outlined in 10CFR20.

3. Confirm that the following Level 2 Acceptance Criterion is satisfied: The radiation doses of plant origin shall meet the following limits depending upon the Radiation Zone in which the radiation measurement point is located:

FSAR Radiation Zone Limit (FSAR Table 12.3-1)

< 0.5 mRem/hr II 5 2.5 mRem/hr ill 5 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.

ConfIrmert fio 0, "I of 1

Attachment V TP-299-010 Revision 3 ST-22 PRESSURE REGULATOR Page 68 of 71 Enter Test Condition and complete the corresponding section. Use a separate copy of this attachment for each Test Condition, Perform the following steps:

In Test Condition A

1. Record power level at which the TURB CV FAST CLOSURE & STOP VLV TRIP BYPASS Alarm (AR-203 window E03) cleared, and Confirm that it cleared before exceeding 26% power. This step is N/A for all other conditions.

Power Level Confirmed By Date In Test Condition A or at 60% power, prior to first Pressure Regulator Step Change test.

N/A this section for all other conditions

2. Confirm Incremental Regulation data and Control Valve position data was collected as required.

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

Confirmed By Date In Test Condition A at 60% power, Perform remaining steps following pressure regulator step changes and failover. N/A this section for all other conditions.

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

5, Confirm ali 78 i ed decay ratios were less or equal t C.5 as equire; by Le'ri r1C-0 at" "1,.3 wIre. less tl an. or equal tt) 10 sei,*:onds as flow r.

1 1i.3 .!reid by LOV,:".1 Date Page 1 of 3

Attachment V TP-299-Q 10 Revision 3 ST-22 PRESSURE REGULATOR Page 69 of 71 In Test Conditions B through D, Perform t he following steps. N/A this section for Test Condition A at 60% power and Test Condition E.

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.

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.

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

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.

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

Confirmed By C ondition td;q5NIN Ste V NIA Nf.;:t...:, ,*;T'SiiikIrte A

.tr.ij.f 2:1 85% to 99cv, 5:1 Page 2 01 3

Attachment V TP-299-010 Revision 3 ST-22 PRESSURE REGULATOR Page 70 of 71 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 3 of 3

Attachment W TP-299-010 Revision 3 Page 71 of 71 ST-24 TURBINE VALVE SURVEILLANCE Enter Test Condition and complete the following. Use a separate copy of this attachment for each Test Condition.

Completion of the following steps satisfies the requirements for ST 24.

1. Confirm reactor did not SCRAM because of the test as required by Level 2 Acceptance Criterion.

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

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

4. Confirm peak heat flux remained below scram trip setting by at least 5.0% as required by Level 2 Acceptance Criterion.

5. Confirm reactor did not isolate because of the test as required by Level 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.

COnfiriref:Ifiy Page of 1