Text

Vermont Yankee, Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and Fiv Effects
	ML060610206
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	02/26/2006
From:	Rademacher N; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	%dam200606, BVY 06-019, TAC MC0761
	Download: ML060610206 (266)
	v • d • e

Entergy Nuclear Northeast Entergy IJuclear Operations, Inc.

Vermont Yankee P.O. Bo: 0500 E n1,te jBrattlebcro, 185 Old Ferry Road VT 05302-0500

~Tel 8022:57 5271 February 26, 2006 Docket No. 50-271 BVY 06-019 TAC No. MC0761 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Vermont Yankee Nuclear Power Station Extended Power Uprate - Regulatory Commitment Information Regarding Steaim Dryer Monitoring and FIV Effects,

References:

1) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, License No. DPR-28 (Docket No. 50-271), Technical Specification Proposed Change No. 263, Extended Power Uprate," BVY 03-80, September 10, 2003

2) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 36, Extended Power Uprate -

Response to NRC's Letter re: License Conditions," BVY C'5-096, October 17, 2005

3) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 33, Extended Power Uprate -

Response to Request for Additional Information," BVY C05-084, September 14, 2005 This letter provides information pursuant to a regulatory commitment made in connection with the application by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.

(Entergy) for a license amendment (Reference 1, as supplemented) to increase the maximum authorized power level of the Vermont Yankee Nuclear Power Station (VYNPS) from 1593 megawatts thermal (MWt) to 1912 MWt.

In Reference 2, Entergy proposed a license condition and made a regulatory commitment to provide information regarding potentially adverse flow effects on plant structures, systems, and components (SSCs) that might result from extended power uprate (EPU) operation. The subject regulatory commitment relates to actions required prior to exceeding 1593 MWt, and states in relevant part:

Al

BVY 06-019 Docket No. 50-271 Page 2 of 3 With regard to [proposed] License Condition 3.M, "Potential Adverse Flow Effects," Entergy will provide information on plant data, evaluations, walkdowns, inspections, and procedures associated with the individual requirements of that license condition to the NRC staff prior to increasing power above 1593 MWt or each specified hold point, as applicable...

Attachment I to this letter is the Steam Dryer Monitoring Plan (SDMP) that will be applicable during power ascension to full EPU conditions. The SDMP will remain in effect until proposed License Condition 3.M expires. The SDMP, together with the EPU Power Ascension Test Procedure (PATP) provide for monitoring, inspecting, evaluating, and prompt action in response to potential adverse flow effects on the steam dryer as a result of power uprate operation.

These actions provide assurance of the continued structural integrity of the steam dryer under EPU conditions.

Included in the SDMP are the "steam dryer stress limit curves." These cuives establish operating limits in accordance with proposed License Condition 3.M (Reference 2). Continuous monitoring of pressure fluctuations from strain gage signals relative to the curves provides assurance of the structural integrity of the steam dryer. If necessary, changes to the SDMP will be made in accordance with the provisions of License Condition 3.M. to this letter are those portions of the power ascension test procedure (PATP) for EPU that are applicable to flow-induced vibration monitoring during power ascension testing for a representative power plateau. Any future changes to the PATP will be made in accordance with governing VYNPS change processes and will be available on-site to NRC inspectors. to this letter provides a description of the data acquisition system that will be used to collect and record signals indicative of pressure loads on the steam dryer. This description is an update to the information provided in Reference 3.

The information contained herewith is provided in accordance with the cited regulatory commitment and in anticipation of actions required to comply with proposed License Condition 3.M. There are no new regulatory commitments contained in this submittal.

If you have any questions or require additional information, please contact Mr. James DeVincentis at (802) 258-4236.

Sincerely, Norman L. Rademacher Director, Nuclear Safety Assurance Vermont Yankee Nuclear Power Station

BVY 06-019 Docket No. 50-271 Page 3 of 3 Attachments (3) cc: Mr. Samuel J. Collins (w/o attachments)

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Richard B. Ennis, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0 8 B1 Washington, DC 20555 USNRC Resident Inspector (w/o attachments)

Entergy Nuclear Vermont Yankee, LL C P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

BVY 06-019 Docket No. 50-271 Attachment I Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and FIV Effects Steam Dryer Monitoring Plan Total number of page; in Attachment I (excluding this cover sheet) is 19.

STEAM DRYER. MONITORING PLAN Vermont Yankee Nuclear Power Station Revision 0 Preparer: Date: O ;a l C. J. Nichols Review er: Date: I f; /00

. M. DeVin Approver: (>2A m / Date: 2-,C.-C6 KJ \R. Dreyf

VYNPS Steam Dryer Monitoring Plan Page 1 of 18 VERMONT YANKEE NUCLEAR POWER STATION STEAM DRYER MONITORING PLAN Introduction and Purpose The Vermont Yankee Steam Dryer Monitoring Plan (SDMP) describes the course of action for monitoring and evaluating the performance of the Vermont Yankee Nuclear Power Station (VYNPS) steam dryer during power ascension testing and operation above 100% of the original licensed thermal power (OLTP), i.e., 1593 MAWt, to the full 120% extended power uprate (EPU) condition of 1912 MWt to verify acceptable performance. The SDMP also addresses long-term actions necessary to implement proposed License Condition 3.M. Through operating limits, periodic surveillances, and required actions, the impact of potentially adverse flow effects on the structural integrity of the steam dryer will be minimized.

Unacceptable steam dryer performance is a condition that could challenge steam dryer structural integrity and result in the generation of loose parts, cracks or tears in the steam dryer that result in excessive moisture carryover. During reactor power operation, performance is demonstrated through the measurement of a combination of plant parameters.

Scope The SDMP is primarily an initial power ascension test plan designed to assess steam dryer performance from 100% OLTP (i.e., 1593 MWt) to 120% OLTP (i.e., 1912 MWt) and to perform confirmatory inspections for a period of time following initial and continued operation at uprated power levels. Power ascension to 120% OLTP will be achieved in a series of power step increases and holds at plateaus corresponding to 80 MWt increments above OLTP. Elements of this plan will be implemented before EPU power ascension testing, and others may continue after power ascension testing.

There are three main elements of the SDMP:

1. Slow and deliberate power ascension with defined hold points and durations, allowing time for monitoring and analysis;

2. A detailed power ascension monitoring and analysis program to trend steam dryer performance (primarily through the monitoring of steam dryer load signals and moisture carryover); and

3. A long term inspection program to verify steam dryer performance at EPU operating conditions.

Several elements of the SDMP also provide for completion of the necessary actions to satisfy the requirements of license conditions associated with the EPU license amendment. A complete tabulation of the provisions of the license condition and the implementing strategy to complete them is contained in Table 3.

Power Ascension VYNPS procedure ERSTI-04-VY1-1409-000, "Power Ascension Test Procedure for Extended Power Conditions 1593 to 1912 MWth," (PATP) will provide controls during power ascension testing and confirm acceptable plant performance. Other procedures may be entered to conduct

VYNPS Steam Dryer Monitoring Plan Page 2 of 18 specialized testing, such as condensate and feedwater testing. The VYNPS power ascension will occur over an extended period with gradual increases in power, hold periods, and engineering analyses of monitored data that must be approved by station management. Relevant data and evaluations will be transmitted to the NRC staff in accordance with the provisions of the license condition. The PATP includes:

1. Power ascension rate of 16 MWt/hr;

2. Hourly monitoring of steam dryer performance during power ascension (required by License Condition 3.M);

3. Four hour holds at each 40 MWt; and

4. Minimum 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months holds at each 80 MWt power plateau to perform steam dryer analysis allowing for NRC review, as appropriate (required by License Condition 3.M),.

Monitoring Plans Table I outlines the steam dryer surveillance requirements during reactor power ascension testing for EPU. The monitoring of moisture carryover and main steam line (MSL) pressure data provide measures; for ensuring acceptable performance of the steam dryer. Frequent monitoring of these parameters will provide early detection capability of off-normal performance.

Proposed License Condition 3.M will require that steam dryer performance criteria are met and prompt action is taken if unacceptable performance is detected. Entergy has established two performance levels (Level 1 criteria and Level 2 criteria) as described in Table ,2for evaluating steam dryer performance during EPU power ascension testing. The Level 1 criteria correspond to the limits specified in the proposed license condition, while the Level 2 criteria are operating action levels that may indicate reductions in margin.

The comparison of measured plant data against defined criteria, based on the steam dryer structural analysis of record, will provide predictive capabilities toward determining steam dryer structural integrity under EPU conditions.

Main Steam Line Strain Gages o During power ascension, steam dryer performance will be monitored hourly through the evaluation of pressure fluctuation data collected from strain gages installed on the MSLs. Entergy has installed strain gages at eight locations on the MSLs in the primary containment and a data acquisition system (DAS) designed to reduce uncertainties in the evaluation of steam dryer loads.

o The strain gage data collected hourly during power ascension will be compared against the stress limit curve that is provided as Figures 1 - 8 of the SDMP and is based on Entergy Calculation VYC-3001. If any frequency peak from the MSL strain gage data exceeds the stress limit curve (Level 1), Entergy will reduce the reactor power to a level at which the stress limit curve is not exceeded.

o Additionally, Entergy will monitor data collected from accelerometers mounted to the main steam piping inside the drywell to provide additional insights into the strain gage signals.

VYNPS Steam Dryer Monitoring Plan Page 3 of 18 o During hold points at each 80 MVt power level above current licensed thermal power, the collected data, along with a comparison to the steam dryer limit curve, will be transmitted to the NRC staff.

o For any circumstance requiring a revision to the steam dryer limit curve, Entergy will resolve uncertainties in the steam dryer analysis and provide the results of that evaluation to the NRC staff prior to further increases in reactor power.

o Entergy will resolve uncertainties in the steam dryer analysis with the NRC staff within 90 days of issuance of the EPU license amendment. If resolution is not made within this time interval, reactor operation will not exceed 1593 MWt. These planned actions are in compliance with proposed License Condition 3.M.

Moisture Carryover o Moisture carryover trending provides an indicator of steam dryer integrity.

o At each 40 MWt step, moisture carryover data will be taken and compared to the predetermined acceptance criteria (Table 2).

Level 1 criteria (0.35%) is based on the maximum analyzed value.

o The data taken at each 80 MWt plateau will be evaluated and documented in the assessment sent to the NRC for information.

Other Monitoring o Plant data that may be indicative of off-normal steam dryer performance will be monitored during power ascension (e.g., reactor water level, steam 'low, feed flow, steam flow distribution between the individual steam lines). Plant data can provide an early indication of unacceptable steam dryer performance. The enhanced monitoring of selected plant parameters will be controlled by the PATP and other plant procedures.

NRC Notifications o In accordance with proposed License Condition 3.M., at discrete power levels, and if the steam dryer stress limit curve (i.e., Level 1 criterion) is exceeded, Entergy will provide notifications to the NRC staff consisting of data and evaluations performed during EPU power ascension testing above 1593 MWt. Detailed discussions regarding new plant data, inspections, and evaluations will be held with NRC staff upon request. The designated NRC point of contact for such information is the NRC Project Manager for the VYNPS EPU.

o The results of the SDMP will be submitted to the NRC staff in a report within 60 days following the completion of all EPU power ascension testing. In addition the final full EPU power performance criteria spectra (i.e., steam dryer stress limiti curve) will be submitted to the NRC staff within 90 days of license amendment issuance.

Contemporary data and results from steam dryer monitoring will be available on-site for review by NRC inspectors as it becomes available. The written report on steam dryer

VYNPS Steam Dryer Monitoring Plan Page 4 of 18 performance during EPU power ascension testing will include evaluations or corrective actions that were required to obtain satisfactory steam dryer performance. The report will include relevant data collected at each power step, comparisons to performance criteria (design predictions), and evaluations performed in conjunction with steam dryer structural integrity monitoring.

Long Term Monitoring The long-.term monitoring of plant parameters potentially indicative of steam dryer failure will be conducted, as recommended by General Electric Service Information Letter 644, Rev. 1 and consistent with License Condition 3.M.

Moisture Carryover Per VYNPS station operating procedure OP-0631, "Radiochemistry," moisture carryover is periodically monitored for moisture carryover during normal plant operations. VYNPS off-normal procedure ON-3178, "Increased Moisture Carryover," provides guidance to evaluate any elevated moisture carryover results including that resulting from potential vessel internals damage. This monitoring will also provide insight into changes in moisture carryover values during changing reactor core configurations (control rod patterns)

Strain Gage Monitoring As the strain gages will remain operational and can provide for future data collection, additional strain gage monitoring will be performed as determined appropriate during the remainder of the operating cycle following EPU implementation.

Inspections The VYNPS steam dryer will be inspected during the refueling outages scheduled for the Spring 2007, Fall 2008, and Spring 2010. The inspections conducted after power uprate implementation will be comparable to the inspection conducted during the Spring 2004 refueling outage and will be in accordance with the guidance in SIL 644, Rev. 1.

Reporting to NRC Steam Dryer Visual Inspections: The results of the visual inspections of the steam dryer conducted during the next three refueling outages shall be reported to the NRC staff within 60 days following startup from the respective refueling outage.

VYNPS Steam Dryer Monitoring Plan Page 5 of 18 Table I Steam Dryer Surveillance Requirements During Reactor Power Operation Above a Previously Attained Power Level Parameter Surveillance Frequency

1. Moisture Carryover Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Notes 1 and 2)

2. Main steam line pressure data Hourly when initially increasing power above a from strain gages previously attained power level AND At least once at every 40 MWt (nominal) power step above 100% OLTP (Note 3)

3. Main steam line data from At least once at every 40 MWt (nominal) power step accelerometers above 100% OLTP (Note 3)

AND Within one hour after achieving every 40 MWt (nominal) power step above 100% OLTI' Notes to Table 1:

1. If a determination of moisture carryover cannot be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of achieving an 80 MWt power plateau, an orderly power reduction shall be made within the subsequent 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to a power level at which moisture carryover was previously determined to be acceptable. For testing purposes, a power ascension step is defined as each power increment of 40 MWt, i.e.,

at thermal power levels of approximately 102.5%, 105%, 107.5%, 110%, 112.5%, 115%,

117.5%, and 120% OLTP. Power level plateaus are nominally every 80 MWt.

2. Provided that the Level 2 performance criteria in Table 2 are not exceeded, when steady state operation at a given power exceeds 168 consecutive hours, moisture carryover monitoring frequency may be reduced to once per week.

3. The strain gage surveillance shall be performed hourly when increasing power above a level at which data was previously obtained. The surveillance of both the strain gage data and MSL pressure data is also required to be performed once at each 40 MWt power step above 1593 MWt and within one hour of achieving each 40 MWt step in power, i.e., at themial power levels of approximately 102.5%, 105%, 107.5%/6, 110%, 112.5%, 115%, 117.5%, and 120% OLTP (i.e., 1593 MWt). If the surveillance is met at a given power level, additional surveillances do not need to be performed at a power level where data had previously been obtained.

If valid strain gage data cannot be recorded hourly or within one hour of initially reaching a 40 MWt power step from at least three of the four MSLs, an orderly power reduction shall be made to a lower power level at which data had previously been obtained. Any such power level reduction shall be completed within two hours of determining that valid data was not recorded.

VYNPS Steam Dryer Monitoring Plan Page 6 of 18 Table 2 Steam Dryer Performance Criteria and Required Actions Performance Criteria Not to be Required Actions if Performance Criteria Exceeded and Required Exceeded Completion Times Level 2: 1. Promptly suspend reactor power ascension until an engineering evaluation concludes that further power ascension isjustified.

Moisture carryover exceeds 0.10/% 2. Before resuming reactor power ascension, the steam dryer OR performance data shall be reviewed as part of an engineering evaluation to assess whether further power ascension can be made

Moisture carryover exceeds without exceeding the Level 1criteria.

0.10%6 and increases by

> 50% over the average of the three previous measurements taken at

> 1593 MWt OR

Pressure data exceed Level 2 Spectra' Level 1: 1. Promptly initiate a reactor power reduction and achieve a previously acceptable power level (i.e., reduce power to a previous step level)

Moisture carryover exceeds within two hours, unless an engineering evaluation concludes that 0.35% continued power operation or power ascension is acceptable.

OR

2. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , re-measure moisture carryover and perform an

Pressure data exceed Level engineering evaluation of steam dryer structural integrity. Ifthe 1Spectral results of the evaluation of steam dryer structural integrity do not support continued plant operation, the reactor shall be placed in a hot shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Ifthe results of the engineering evaluation support continued power operation, implement steps 3 and 4 below.

3. Ifthe results of the engineering evaluation support continued power operation, reduce further power ascension step and plateau levels to nominal increases of 20 MWt and 40 MWt, respectively, for any additiona I power ascension.

4. Within 30 days, the transient pressure data shall be used to calculate the steam dryer fatigue usage to demonstrate that continued power operation isacceptable.

1The EPU spectra shall be determined and documented in an engineering calculation or report. Acceptable Level 2 spectra shall be based on maintaining < 80% of the ASME allowable alternating stress (Sa) value at 1011 cycles (i.e., 10.88 ksi). Acceptable Level 1 Spectra shall be based on maintaining the ASME Sa at 1011 cycles (i.e., 13.6 ksi).

VYNPS Steam Dryer Monitoring Plan Page 7 of 18 Table 3 Steam Drver License Conditions License Condition Requirement Implementing Actions 3.M.1.a Entergy shall monitor hourly the 32 During initial power ascension above 1593 MWt, main steam line (MSL) strain gages data from at least 32 strain gages will be collected during power ascension above 1593 and evaluated by Entergy's power ascension test MWt for increasing pressure team to verify that acoustic signals indicative of fluctuations in the steam lines. increasing pressure fluctuations in the steam lines are not challenging the steam dryer stress limit curve. Monitoring will be conducted hourly during any power ascension above a previously attained power level.

(Reference ERSTI-04-VY1-11409-0C0)

(Reference PCRS tracking item WT-VTY-2005-00000-01803) 3.M.1.b Entergy shall hold the facility for 24 The PATP has established test plateau increments hours at 105%, 110%, and 115% of of approximately 80 MWt (corresponding to 105%,

OLTP (i.e., 1593 MWt) to coIled: 110%, and 115% of 1593 MWt). Reactor power will data from the 32 MSL strain gages not be increased above the plateau for a minimum required by License Condition of 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . During the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of steady 3.M.1.a, conduct plant inspections state operation at each plateau, strain gage data and walkdowns, and evaluate steam will be collected from all available strain gages dryer performance based on these (minimum of 32) and evaluated to demonstrate data; shall provide the evaluation to acceptable steam dryer performance. Additionally, the NRC staff by facsimile or moisture carryover measurements will be made at electronic transmission to the NRC each plateau and every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during power project manager upon completion of ascension testing. At the 80 MWt plateau hold the evaluation; and shall not points, Entergy will conduct plant walkdowns and increase power above each hold inspections of plant equipment, including piping and point until 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after the NRC components identified as potentially vulnerable to project manager confirms receipt of flow-induced vibration (FIV) in accordance with the the transmission. PATP and other plant procedures. Steam dryer performance will be evaluated based on these data.

The 24-hour period and the 96-hour period may overlap once the transmittal is provided to the NRC staff.

The evaluations of steam dryer perlormance, based on the data collected during each of the 80 MWt plateaus, as well as the results of walkdowns and other measurements of FIV for various piping and plant components, will be provided lo the NRC staff.

Arrangements have been made for electronic transmission through email and/or uploading to a

VYNPS Steam Dryer Monitoring Plan Page 8 of 18 License Condition Requirement Implementing Actions designated website. Upon the NRC Project Manager confirming receipt of the steam dryer data and performance evaluation, the 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months of hold time will commence. Power will riot be increased above each of the 80 MWt hold points until the expiration of the 96-hour hold.

If during the hold periods, or at any other time, the NRC staff requests a discussion or requires clarification of the engineering evaluations provided in fulfillment of this requirement, Entergy will promptly arrange for such discussions. Entergy will maintain a power ascension control center, including management oversight, available 24/7 on-site during power increases to previously unattained power levels.

(Reference ERSTI-04-VYl-1409-000)

(Reference PCRS tracking item WT-VTY-2005-00000-01803) 3.M.1.c If any frequency peak from the MSL. The steam dryer stress limit curve provided strain gage data exceeds the limit herewith contains Level 1 and Level 2 criteria. If curve established by Entergy frequency peaks from MSL strain gage data exceed Nuclear Operations, Inc. and either Level 1 or Level 2 criteria, prompt action will submitted to the NRC staff prior to be taken in response to the potential adverse flow operation above OLTP, Entergy effects that might result. Similar actions will occur if Nuclear Operations, Inc. shall return moisture carryover is excessive and previously the facility to a power level at which established Level 1 or Level 2 criteria are the limit curve is not exceeded. exceeded. The Level 2 criteria represent a Entergy Nuclear Operations, Inc. conservative action level for evaluation and close shall resolve the uncertainties in the monitoring of steam dryer performance-not a limit.

steam dryer analysis, document the The Level 1 criteria represent analytical limits and continued structural integrity of the additional actions may be warranted.

steam dryer, and provide that documentation to the NRC staff by If any frequency peak from the MISL strain gage facsimile or electronic transmission data exceeds the Level 1 steam dryer stress limit to the NRC project manager prior to curve, Entergy will reduce reactor power to a power further increases in reactor power. level at which the limit curve is not exceeded.

(Reference ERSTI-04-VY1-1409-000)

Prior to any further increase in power above the reduced power level, Entergy will (1) resolve the uncertainties in the steam dryer analysis, (2) evaluate and document the adequate structural integrity of the steam dryer, and (3) provide that

_ documentation to the NRC staff. Any revision to the

VYNPS Steam Dryer Monitoring Plan Page 9 of 18 License Condition Requirement Implementing Actions limit curve based on this evaluation will be provided to the NRC staff.

(Reference PCRS tracking item WT-VTY-2005-00000-01803) 3.M.1.d In addition to evaluating the MSL Accelerometers mounted on MSI piping will be strain gage data, Entergy Nuclear monitored on an hourly basis during power Operations, Inc. shall monitor ascension testing to identify if resonances are reactor pressure vessel water level increasing above nominal levels in proportion to instrumentation or MSL piping MSL strain gage data. If abnormally increasing accelerometers on an hourly basis resonant frequencies are detected, power during power ascension above ascension will be halted. Prior to any further OLTP. If resonance frequencies are increase in power, Entergy will (1) evaluate and identified as increasing above document the adequate structural integrity of the nominal levels in proportion to strain steam dryer, and (2) provide that documentation to gage instrumentation data, Entergy the NRC staff.

Nuclear Operations, Inc. shall stop (Reference ERSTI-04-VYl -1409-000) power ascension, document the (Reference PCRS tracking item WT-VTY-2005-continued structural integrity of the 00000-01803) 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.

3.M.1.e Following start-up testing, Entergy After collecting strain gage data at approximately Nuclear Operations, Inc. shall the EPU full power level, Entergy will resolve the resolve the uncertainties in the uncertainties in the steam dryer analysis and steam dryer analysis and provide provide documentation of the resolution to the NRC that resolution to the NRC staff by staff. If these actions cannot be achieved within 90 facsimile or electronic transmission days of issuance of the license amendment, reactor to the NRC project manager. If the power will be limited to 1593 MWt. This uncertainty uncertainties are not resolved within evaluation may be prepared and provided to the 90 days of issuance of the license NRC prior to reaching EPU full power levels amendment authorizing operation at associated with any proposed revision to the steam 1912 MWt, Entergy Nuclear dryer limit curve.

Operations, Inc. shall return the (Reference PCRS tracking item WT-VTY-2005-facility to OLTP. 00000-01803) 3.M.2.a Prior to operation above OLTP, To enhance performance and improve the accuracy Entergy Nuclear Operations, Inc. of the steam dryer measurement system, Entergy shall install 32 additional strain has installed 48 strain gages on MSL piping and will gages on the main steam piping and maintain a minimum of 32 operable strain gages shall enhance the data acquisition during power ascension testing. The data system in order to reduce the acquisition system (DAS) was upgraded to reduce measurement uncertainty the uncertainty associated with the ACM.

VYNPS Steam Dryer Monitoring Plan Page 10 of 18 License Condition Requirement Implementing Actions associated with the acoustic circuit (Reference Entergy VYNPS Temporary Alteration model (ACM). TA-2005-15 R1) 3.M.2.b In the event that acoustic signals If acoustic signals indicative of increasing pressure are identified that challenge the limit fluctuations in the steam lines Eire identified as curve during power ascension challenging the steam dryer stress limit curve (i.e.,

above OLTP, Entergy Nuclear Level 1 criterion), in addition to reducing reactor Operations, Inc. shall evaluate power to a previously acceptable power level, steam dryer loads and re-establish Entergy will conduct an evaluation and re-establish the limit curve based on the new the limit curve based on the latest strain gage data.

strain gage data, and shall perform As part of the redevelopment of the limit curve, a frequency-specific assessment of Entergy will prepare a frequency-specific ACM uncertainty at the acoustic assessment of ACM uncertainty at the acoustic signal frequency. signal frequency. This uncertainty evaluation may be prepared and provided to the NRC in advance of this condition being met.

(Reference ERSTI-04-VY'l-1409-000) 3.M.2.c After reaching 120% of OLTP, After collecting strain gage data at approximately Entergy Nuclear Operations, Inc. the EPU full power level, Entergy will establish the shall obtain measurements from the steam dryer flow-induced vibration load fatigue MSL strain gages and establish the margin for the facility, update the steam dryer stress steam dryer flow-induced vibration report, and re-establish the stress limit curve with load fatigue margin for the facility, the updated ACM load definition and revised update the steam dryer stress instrument uncertainty. This information will be report, and re-establish the steam included in the report to the NRC staff being made dryer monitoring plan (SDMP) limit in accordance with License Condition 3.M.1.e.

curve with the updated ACM load (Reference PCRS tracking item WT-VTY-2006-definition and revised instrument 00000-00249) uncertainty, which will be provided to the NRC staff.

3.M.2.d During power ascension above If an evaluation or analysis of the structural integrity OLTP, if an engineering evaluation of the steam dryer is required because acoustic is required in accordance with the signals indicative of increasing pressure fluctuations SDMP, Entergy Nuclear Operations, in the steam lines are identified as potentially Inc. shall perform the structural challenging the steam dryer stress limit curve (i.e.,

analysis to address frequency Level 1 criterion), Entergy will address frequency uncertainties up to +/-10% and uncertainties up to + 10% and assure that peak assure that peak responses that fall responses that fall within this uncertainty band are within this uncertainty band are addressed. This uncertainty evaluation may be addressed. prepared and provided to the NRC in advance of this condition being met.

(Reference ERSTI-04-VY1-1409-000)

VYNPS Steam Dryer Monitoring Plan Page 11 of 18 License Condition Requirement Implementing Actions 3.M.2.e Entergy Nuclear Operations, Inc. The revised SDMP provides long-term monitoring of shall revise the SDMP to reflect steam dryer performance in accordance with GE long-term monitoring of plant SIL 644 Rev. 1.

parameters potentially indicative of (Reference PCRS tracking item WT-VTY-2006-steam dryer failure; to reflect 00000-00250) consistency of the facility's steam dryer inspection program with The SDMP and the PATP identify the NRC Project General Electric Services Manager for the VYNPS EPU as the point of Information Letter 644, Revision 1; contact for providing SDMP information during and to identify the NRC Project power ascension.

Manager for the facility as the point (Reference ERSTI-04-VYl-1409-000) of contact for providing SDMFP information during power ascension. For moisture carryover, procedures OP-0631 and ON-3178 provide for long-term monitoring and controls.

3.M.2.f Entergy Nuclear Operations, Inc. The final EPU steam dryer load definition will be shall submit the final extended included in the report provided to the NRC staff in power uprate (EPU) steam dryer accordance with License Conditions 3.M.1.e. and load definition for the facility to the 3.M.2.c.

NRC upon completion of the power (Reference PCRS tracking item WT-VTY-2006-ascension test program. 00000-00251) 3.M.2.g Entergy Nuclear Operations, Inc. Entergy letter BVY 06-019 forwards the FIV-related shall submit the flow-induced portions of the EPU power ascension test vibration related portions of the EPU procedure to the NRC. (Reference ERSTI-04-VYl-startup test procedure to the NRC., 1409-000) including methodology for updating the limit curve, prior to initial power The methodology for updating the steam dryer ascension above OLTP. stress limit curve is as follows:

Prerequisite: Generate report resolving uncertainties in the steam dryer analysis.

1. Collect representative data from 32 strain gages at eight MSL locations.

2. Using a plant-specific ACM, analyze strain gage data to determine steam dryer loads.

3. Input ACM loads into a finite element model to determine dryer stresses.

4. Perform an updated uncertainty evaluation.

5. Generate revised steam dryer stress limit curve(s).

(Reference PCRS tracking item WT-VTY-2006-00000-00252)

VYNPS Steam Dryer Monitoring Plan Page 12 of 18 License Condition Requirement Implementing Actions 3.M.3(a) Entergy shall prepare the EPLI The steam dryer stress limit curve to be applied for startup test procedure to include the evaluating steam dryer performance during power stress limit curve to be applied for ascension is provided herewith. The limit curve was evaluating steam dryer developed on the basis of calculation VYC-3001, performance. which is incorporated by reference into the EPU PATP.

(Reference ERSTI-04-VYl-1409-OC)O) 3.M.3(b) Entergy shall prepare the EPLI Specific hold points and durations are specified in startup test procedure to include the PATP.

specific hold points and their (Reference ERSTI-04-VYl-1409-000) duration during EPU poweir ascension.

3.M.3(c) Entergy shall prepare the EPLI Activities to be accomplished during hold points are startup test procedure to include specified in the PATP.

activities to be accomplished during (Reference ERSTI-04-VYl-1409-000) hold points.

3.M.3(d) Entergy shall prepare the EPLI Plant parameters to be monitored are specified in startup test procedure to include Attachment 9 to the PATP.

plant parameters to be monitored. (Reference ERSTI-04-VY1-1409-000) 3.M.3(e) Entergy shall prepare the EPLI Inspections and walkdowns to be conducted for startup test procedure to include steam, feedwater, and condensate systems and inspections and walkdowns to be components during hold points are specified in conducted for steam, feedwater, Attachment 9 to the PATP.

and condensate systems and (Reference ERSTI-04-VYl-1409-000) components during the hold points.

3.M.3(f) Entergy shall prepare the EPU Methods to be used to trend plant parameters are startup test procedure to include specified in Attachment 9 to the PATP.

methods to be used to trend plant (Reference ERSTI-04-VY1-1409-000) parameters.

3.M.3(g) Entergy shall prepare the EPUI Acceptance criteria for monitoring and trending startup test procedure to include! plant parameters, and conducting the walkdowns acceptance criteria for monitoring and inspections are specified in Attachment 9 to the and trending plant parameters, and PATP. (Reference ERSTI-04-VY1-1409-000) conducting the walkdowns and inspections.

3.M.3(h) Entergy shall prepare the EPU Actions to be taken if acceptance criteria are not startup test procedure to include satisfied are specified in the PATP.

actions to be taken if acceptance (Reference ERSTI-04-VY1-1409-000) criteria are not satisfied.

VYNPS Steam Dryer Monitoring Plan Page 13 of 18 License Condition Requirement Implementing Actions 3.M.3(i) Entergy shall prepare the EPLI Verification of the completion of commitments and startup test procedure to include planned actions specified in the license amendment verification of the completion of application and all supplements to the application in commitments and planned actions support of the EPU license amendment request specified in the license amendment pertaining to the steam dryer is specified in the application and all supplements to PATP.

the application in support of the (Reference ERSTI-04-VYI-1409-000)

EPU license amendment request pertaining to the steam dryer.

3.M.4 When operating above OLTP, the These restrictions are provided in l:he PATP and/or operating limits, required actions, the SDMP.

and surveillances specified in the (Reference ERSTI-04-VYI-1409-000)

SDMP shall be met. The following key attributes of the SDMP shall not be made less restrictive without prior NRC approval:

a. During initial power ascension testing above OLTP, each test plateau increment shall be approximately 80 MWt;

b. Level 1 performance criteria; and

c. The methodology for establishing the stress spectra used for the Level I and Level 2 performance criteria.

Changes to other aspects of the SDMP may be made in accordance

_with the guidance of NEI 99-04.

3.M.5 During each of the three scheduled The VYNPS steam dryer will be inspected during refueling outages (beginning with the refueling outages scheduled for the Spring the spring 2007 refueling outage), 2007, Fall 2008, and Spring 2010. The inspections a visual inspection shall be conducted after power uprate implementation will conducted of all accessible, be comparable to the inspections conducted during susceptible locations of the steam the Spring 2004 and Fall 2005 refueling outages dryer, including flaws left "as is" and will be in accordance with the guidance in SIL and modifications. 644, Rev. 1.

(Reference PCRS tracking item WT-VTY-2006-00000-00253)

(Reference PCRS tracking item WT-VTY-2006-00000-00254)

VYNPS Steam Dryer Monitoring Plan Page 14 of 18 License Condition Requirement Implementing Actions (Reference PCRS tracking item WT-VTY-2006-00000-00255) 3.M.6 The results of the visual The VYNPS steam dryer will be inspected during inspections of the steam dryer the refueling outages scheduled for the Spring conducted during the three 2007, Fall 2008, and Spring 2010. The inspections scheduled refueling outages conducted after power uprate implementation will (beginning with the spring 2007 be comparable to the inspections conducted during refueling outage) shall be reported the Spring 2004 and Fall 2005 refueling outages to the NRC staff within 60 days and will be in accordance with the guidance in SIL following startup from the 644, Rev. 1. The results will be documented in a respective refueling outage. The report and submitted to the NRC within 60 days results of the SDMP shall be following completion of all EPU power ascension submitted to the NRC staff in a testing.

report within 60 days following the (Reference PCRS tracking item WT-VTY-2006-completion of all EPU power 00000-00256) ascension testing. (Reference PCRS tracking item WT-VTY-2006-00000-00257)

(Reference PCRS tracking item WT-VTY-2006-00000-00258) 3.M.7 The requirements of paragraph When operating above 1593 M"it, the operating 3.M.4 above for meeting the SDMP limits, required actions, and surveillances specified shall be implemented upon in the SDMP will be met. Those key attributes of issuance of the EPU license the SDMP specified in License Condition 3.M.4 will amendment and shall continue not be made less restrictive without prior NRC until the completion of one full approval.

operating cycle at EPU. If an (Reference PCRS tracking item WT-VTY-2006-unacceptable structural flaw (due 00000-00259) to fatigue) is detected during the subsequent visual inspection of the steam dryer, the requirements of paragraph 4 shall extend another full operating cycle until the visual inspection standard of no new flaws/flaw growth based on visual inspection is satisfied.

3.M.8 This license condition shall expire (Reference PCRS tracking item WT-VTY-2006-upon satisfaction of the 00000-00260) requirements in paragraphs 5, 6, and 7 provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is due to fatigue.

VYNPS Steam Dryer Monitoring Plan Page 15 of 18 MISL A Upper a,

1Ii 150 200 250 0 50 100 Frequency, Hz I -LC_2 Ave-MSLAUpper -LC_1 AveMSL_AUpper

~1I Fiaure 1: Steam Dryer Stress Limit Curve - MSL 'A' UDer NISL A Lower 1.OE+00 m_777

_RAW 1.OE-01 1.OE-02 1.OE-03 1.OE-04 I .OE-05 1.OE-06 0 50 10( 150 200 250 Frequency, Hz

-LC_2 Ave_MSL_A Lower -LC_I AveMSLA_Lower Figure 2: Steam Dryer Stress Limit Curve - MSL 'A' Lower

VYNPS Steam Dryer Monitoring Plan Page 16 of 18 HISL B Upper M:' ' i C---'S-

. ' . ., .t -: , -'7 .,

2 -$ _- _ __;_ _ _ _ __-_ _ _ _ _ __1= _

1iQE-01 1.OE-03 ____'__

1.0E-04 -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-=

1.OE 1a _______ _ _

1.OE 0 50 100 150 200 25(

Frequency, Hz

- LC_2 Ave-MSLB-Upper -LC_1 Ave_MSL_BUpper Fiqure 3: Steam Dryer Stress Limit Curve - MSL 'B' UDrer lISL B Lower N

ii 50 100 150 200 250 Frequency, Hz

-LC_2 AveMSLBLower -LC_I AveMSL_B_Lower Figure 4: Steam Dryer Stress Limit Curve - MSL 'B' Lower

VYNPS Steam Dryer Monitoring Plan Page 17 of 18 IVSL C Upper N

z ~rv 1E-0 0 50 100 150 200 250 Frequency, Hz

- LC_2 Ave MSL_CUpper -LC 1 AveMSL_C Upper Figure 5: Steam Dryer Stress Limit Curve - MSL 'C' Upper MSL C Lower zN 0 50 1DO 150 200 25 0 Frequency, Hz

-IC_2AveMSLCLower -LC_ Ave_MSL_C_Lower Figure 6: Steam Dryer Stress Limit Curve - MSL 'C' Lower

VYNPS Steam Dryer Monitoring Plan Page 18 of 18 MSL D Upper f;-ff- ;- -, -E' ,. ' ': 0'"S ', d'7d'.

0 50 100 150 200 250 Frequency, Hz I -LC_2AveMSLDUpp~r -LC_1 Ave_MSL_D_Upper A Figure 7: Steam Drve!r Stress Limit Curve - MSL 'D' Upper MIISL D Lower 1.OE-01 I .OE-02 zq Z' 1.OE-03 1.OE-04 1.OE-05 I .OE-06 50 1(0 150 200 250 Frequency, Hz

-LC_2Ave_MSL_D_Lower -LC_1AveMSL_D_Lower 7 Figure 8: Steam Dryer Stress Limit Curve - MSL 'D' Lower

BVY 06-019 Docket No. 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and FIV Effects Power Ascension Test Procedure (FIV Portions)

Total number of pages in Attachment 2 (excluding this cover sheet) is 228.

Power Ascension Testing for Extended Power Uprate Conditions ATTACHMENT 9.6 TEST PROCEDURE COVER SHEET Sheet I of I TEST COVER SHEET TEST TYPE: E] ERT Procedure 0 ERSTI Procedure Page 1 of 118 TEST#: ERSTI-04-VY1-1409-000 Quality Class: 0 QR E1 NQR TEST Power Ascension Test Procedure for Extended Power Conditions 1593 to 1912 TITLE: MWth REVIEW (Print/Sign/Date)

Test Engineer (IE): Brvan Croke . 11 c. /

Technical Reviewer: Paul Stello _ _ _ _ _ L72r/l CROSS-DISCIPLINE REVIEW, 'S VD WZJ-C Operations Department: J / S'/o Chemistrv C\5k z S 2-(o-ox Organization:

RadiationProtection : IS Engineering -,; /c///6 Organization: Organization Q _alitAssurance :_____Maintenance-:.

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ADDITIONAL ERSTI (ONLY) PROCEDURE REQUIREMENTS R r JAiv. 4' ENN-LI-1 00 Review: 0D Attached 0 Other (0091R Review)

IOCFR50.59 Evaluation: tA Not Required O Attached El Other OSRC Approval El Not Required Mtg No,-jcxLt Date:) l)]/?; Chair n n n kI 1 APPROVAL(PrinUSign/Date)

TE Supervisor: Craig Nichols TEST COMPLETION REVIEW / ACCE(TANCE Summary of Test Results:

Test Engineer (TE): /

TE Supervisor: /

ERSTI-04-VY1- 1409-000 Page 1 of44 III

Power Ascension Testing for Extended Power Uprate Conditions Table of Contents

1. OBJECTIVE........................................................................................................................................................5 1.1. Intent .................. 5 1.2. Discussion .................. 8 1.3. Definitions .................. 9 1.4. Responsibilities ................. 14

2. REFERENCES..17

3. APPARATUS/TEST EQUIPMENT .. 21

4. PRECAUTIONS AND LIMITATIONS .. 22

5. TERMINATION CRITERIA .. 24

6. PREREQUISITES........................................................................................................................................... 27

7. PROCEDURE.................................................................................................................................................. 47 7.1. 1593 MWth .48 7.2. Increasing to 1633 MWth .51 7.3. Increasing to 1673 MWth .54 7.4. Increasing to 1712 MWth .68 7.5. Increasing to 1752 MWth .71 7.6. Increasing to 1792 MWth .85 7.7. Increasing to 1832 MWth .88 7.8. Increasing to 1872 MWth .102 7.9. Increasing to 1912 MWth .105 7.10. Remaining at 1912 MWth 115

8. RESTORATION............................................................................................................................................ 116

9. ATTACHM ENTS.......................................................................................................................................... 116 IA Dryer Data Collection 1593 MWth lB Dryer Data Collection 1609 MWth IC Dryer Data Collection 1625 MWth ID Dryer Data Collection 1633 MWth 1E Dryer Data Collection 1649 MWth 1F Dryer Data Collection 1665 MWth 1G Dryer Data Collection 1673 MWth 1H Dryer Data Collection 1689 MWth 11 Dryer Data Collection 1705 MWth 1J Dryer Data Collection 1712 MWth 1K Dryer Data Collection 1728 MWth IL Dryer Data Collection 1744 MWth IM Dryer Data Collection 1752 MWth ERSTI-04-VY 1-1409-000 Page 2 of 118

Power Ascension Testing for Extended Power Uprate Conditions IN Dryer Data Collection 1768 MWth 10 Dryer Data Collection 1784 MWth 1P Dryer Data Collection 1792 MWth 1Q Dryer Data Collection 1808 MWth 1R Dryer Data Collection 1824 MWth 1S Dryer Data Collection 1832 MWth IT Dryer Data Collection 1848 MWth 1U Dryer Data Collection 1864 MWth 1V Dryer Data Collection 1872 MWth 1W Dryer Data Collection 1888 MWth IX Dryer Data Collection 1904 MWth lY Dryer Data Collection 1912 MWth 2A Flow Induced Vibration Data 1593 MWth 2B Flow Induced Vibration Data 1633 MWth 2C Flow Induced Vibration Data 1673 MWth 2D Flow Induced Vibration Data 1712 MWth 2E Flow Induced Vibration Data 1752; MWth 2F Flow Induced Vibration Data 1792: MWth 2G Flow Induced Vibration Data 1832; MWth 2H Flow Induced Vibration Data 1872: MWth 21 Flow Induced Vibration Data 1912 MWth 3 Radiation Surveys 4 Core Perfonnance Data Sheet various MWth 5A Moisture Carryover 1633 MWth SB Moisture Carryover 1673 MWth SC Moisture Carryover 1673 MWth SD Moisture Carryover 1673 MWth 5E Moisture Carryover 1673 MWth SF Moisture Carryover 1712 MWth SG Moisture Carryover 1752 MWth SH Moisture Carryover 1752 MWth 5I Moisture Carryover 1752 MWth 5J Moisture Carryover 1752 MWth 5K Moisture Carryover 1792 MWth 5L Moisture Carryover 1832 MWth 5M Moisture Carryover 1832 MWth 5N Moisture Carryover 1832 MWth 50 Moisture Carryover 1832 MWth 5P Moisture Carryover 1872 MWth 5Q Moisture Carryover 1912 MWth 5R Moisture Carryover 1912 MWth SS Moisture Carryover 1912 MWth ST Moisture Carryover 1912 MWth ERSTI-04-Y 1-1409-000 Page 3 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6A Feedwater Runout Data Collection 1673 MWth 6B Feedwater Runout Data Collection 1752 MWth 6C Feedwater Runout Data Collection 1832 MWth 6D Feedwater Runout Data Collection 1912 MWth 7A Feedwater Level Changes 1673 MWth 7B Feedwater Level Changes 1752 MWth 7C Feedwater Level Changes 1832 MWth 7D Feedwater Level Changes 1912 MWth 8A MHC Pressure Change 1673 MWth 8B MHC Pressure Change 1752 MWth 8C MHC Pressure Change 1832 MWth 8D MHC Pressure Change 1912 MWth 9A System Data 1593 MWth 9B System Data 1673 MWth 9C System Data 1572 MWth 9D System Data 1832 MWth 9E System Data 1912 MWth 10 Site Boundary Dose Measurements Various MWth 1OA Chemistry Data 1673 MWth lOB Chemistry Data 1572 MWth 1OC Chemistry Data 1832 MWth lOD Chemistry Data 1912 MWth 1lA Recombiner Performance Data 1673 MWth 1lB Recombiner Performance Data 1752 MWth 11 C Recombiner Performance Data 1832 MWth 1ID Recombiner Performance Data 1912 MWth 12 Signature Identification Log 13 Test Deficiency Log 14 Performance Summary 15 ENN-LI- 100 Process Applicability Determination 16 ENN-LI-101, 10.59 Screen 17 Risk Management Worksheet VYAPF 0172.02 ERSTI-04-VY 1-1409-000 Page 4 of 118

Power Ascension Testing for Extended Power Uprate Conditions Objective The objective is to confirm acceptable plant performance for operation at extended power uprate to 1912 MWth per Nuclear Change 2005-1409, EPU.

This Test Instruction provides step by step guidance and verification for performing Power Ascension Testing requirements for Extended Power Uprate (EP]J) conditions.

The Test Instruction supplements OP-0105, Reactor Operations, to provide direction to maneuver the plant from 1593 MWtI [83.32% LPU] to 1912 MWth [100.00% LPU].

First and foremost is the safety of the reactor, nuclear plant and personnel. This procedure was written with this specifically in mind, providing the necessary criteria, instruction, oversight, and precautions to successfully execute the Power Ascension Testing for Extended Power Uprate Conditions.

Separate procedures are written to:

Determine the maximum safe power level when MSIV, turbine bypass and turbine stop valve testing can be performed. This determination is accomplished separately from this procedure.

Demonstrate plant response to a condensate pump trip.

1.1. Intent 1.1.1. Document the plant physical modifications, instrumentation setpoint changes, and prerequisite testing have been satisfactorily completed and to meet the established acceptance criteria to raise reactor power above 1593 MWth. to 1912 MWth.

1.1.2. Implement tests contained in EPU Project Task Report VY-RPT 00041, "T1005: Startup Test Specifications" 1.1.2.1. Maintain control of and knowledge of the reactor coolant chemistry and radiochemistry at extended uprate conditions.

ERSTI-04-VY1 -1409-000 Page 5 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.1.2.2. Monitor radiation levels at the extended uprate power conditions to assure that personnel exposures are maintained ALARA, radiation survey maps are accurate, radiation zones are properly posted, site boundary doses are as expected, and offsite boundary doses comply with state and federal regulations.

1.1.2.3. Measure and evaluate core thermal power and fuel thermal margins to ensure a careful, monitored approach to the next power uprate level.

1.1.2.4. Monitor feedwater level control system for acceptable reactor water level control.

1.1.2.5. Confinn acceptable calibration of the feedwater flow elements at uprated power conditions.

1.1.3. Demonstrate that affected plant parameters and equipment performance remains within the acceptable limits as power is increased from 1593 MWth to 1912 MWth.

1.1.4. Monitor plant system response via the System Engineering System Monitoring Plans.

1.1.5. Provide Shift Operations personnel clear instructions on testing and operational maneuvers to be performed as power level is increased in a step-wise manner to assure safe plant operation.

1.1.6. Provide management reviews and approvals of the test data and the authorization needed to increase power level in a safe, controlled, step wise manner.

1.1.7. Assure that procedures requiring revision to operate at uprated power conditions have been revised as required and are available to plant personnel.

1.1.8. Assure that regulatory commitments have been completed as required to increase power above 1593 MWth. This includes commitments contained within the License Amendment Request (LAR),

correspondence to the NRC Request for Additional Information (RAI),

the NRC issued Safety Evaluation Report (SER) and any license conditions. This will be accomplished via the Pre-requisite section of this procedure.

ERSTI-04-V/Y1-1409-000 Page 6 of 118

Power Ascension Testing for, Extended Power Uprate Conditions 1.1.9. Verify that training has been completed to meet licensing commitments and provide safe operation of the plant.

1.1.10. Document and collect data, including baseline data at 1593 MWth, which will be used to prepare an EPU Test Report to be submitted to the NRC upon completion.

ERSTI-04-VY1-1409-000 Page 7 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.2. Discussion 1.2.1. The EPU Project utilized a generic methodology from General Electric for evaluating plant systems and equipment for operating at uprated power levels. This methodology provided system, program, and equipment task evaluations, which identified the acceptability to operate at an increased power level. These task evaluation documents provided input into the testing program which is implemented by this test procedure.

1.2.2. The steps contained in this document were a culmination of inputs from numerous sources. The GE Licensing Topical Report (GELTR) required operational tests for systems which have revised performance requirements because of the extended power uprate. A test plan was submitted with the License Amendment Request, which specified the operational tests to be performed. A review of the original start-up test specifications was completed and tests were selected based on the change resulting from the extended power uprate. TestL requirements were also added to this procedure based on the System Task Reports to ensure that analyses were accurate and closely monitored. Finally, test requirements were added based on Engineering judgment, discussion with plant personnel and Lessons Learned from other plant power uprates.

1.2.3. Test requirements that are satisfied by completion of existing surveillances, calibrations or post modification testing need not be repeated for the purposes of this procedure unless specifically identified in this procedure.

1.2.4. Plant maneuvers and operation shall be performed in accordance with applicable VY Station Procedures including power changes in accordance with OP 2404, Determination and Implementation of Rod Movement Sequences and OP 0105, Reactor Operations.

1.2.5. A Power Ascension Control Center (PACC) is established to support implementing this procedure. Personnel from various functional areas, together with senior managers, are assigned to provide continuously available resources to address issues that may arise during the performance of this procedure. Additional peer assessments and reviews will be available, if required.

ERSTI-04-VYl-1409-000 Page 8 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.3. Definitions 1.3.1. CPPU - Constant Pressure Power Uprate - Operating at increased steam and feedwater flows without increasing maximum reactor recirculation flow or reactor vessel operating pressure.

1.3.2. Decay ratio - is a term used to describe the amplitude dampening of an oscillatory signal.

Decay ratio is less than 0.25 if there are no more than two positive peaks. IF more than two positive peaks exist, THEN decay ratio must be calculated as follows:

Draw baseline through inflection points of trace.

Amplitudes of peaks should be measured from this reference line, e.g., AO, Al, A2, A3, and A4 as shown in Figure below.

Calculate ratios of amplitudes between successive peaks of same polarity, e.g., A2/AO, A3/A1, A4/A2.

. Decay ratio determined by averaging all ratios determined in previous step, e.g.,

Decay Ratio = (A2/AO + A3/A1 + A4/A2) /3.

ERSTI-04-'MY1- 1409-000 Page 9 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.3.3. EPR - Electrical Pressure Regulator - the electrical/mechanical system which controls the turbine control valves and turbine bypass valves based on main steam pressure. This is the primary turbine pressure control system.

1.3.4. FIV - Flow Induced Vibration 1.3.5. FRV - Feedwater Regulating Valves - air operated feedwater control valves FCV-6-12A and FCV-6-12B that throttle reactor feedwater flow based on signals received from the Feedwater Level Control System.

1.3.6. Intrusive Activities - activities that do have the potential to or change parameters associated with reactor power including backwashing and pre-coating condensate demineralizers, pump swaps, raising or lowering reactor power, changing reactor pressure, etc.

1.3.7. Lead Test Performer - In accordance with ENN-DC-1 17, a person or group assigned by the Test Engineer to assist in the performance of an ERT or STI. The Lead Test Performer may perform the duties of the Test Engineer, in performing the test, as directed by the Test Engineer.

1.3.8. LPU - License Power Uprate = 1912 MWth 1.3.9. MHC Mechanical Hydraulic Control - the combined pressure control system made up of the EPR and MPR.

1.3.10. MPR - Mechanical Pressure Regulator - the mechanical system which controls the turbine control valves and turbine bypass valves based on main steam pressure. This is the backup turbine pressure control system.

1.3.11. Non intrusive activities - activities that do not change any parameters associated with reactor power including data collection, obtaining chemistry samples, etc.

1.3.12. RE - Reactor/Computer Engineering 1.3.13. Responsible Engineer - in accordance with ENN-DC-1 17, an individual assigned primary responsibility and cognizance for development of an ER Response.

ERSTI-04-VY1-1409-000 Page lOofll8

Power Ascension Testing for Extended Power Uprate Conditions 1.3.14. Termination and Hold Criteria 1.3.14.1. Level .: Criteria associated with plant safety.

When a criterion is not met, TERMINATE the test and:

1.3.14.1.1. Hold at the most secure point and place the plant in a condition that is judged to be satisfactory and safe, based upon prior testing, reducing power if necessary.

1.3.14.1.2. Follow plant operating procedures, test procedures or the Technical Specifications on the decision of actions to be taken.

1.3.14.1.3. Generate a CR (condition report) and pursue resolution of the problem through investigating related adjustments as well as measurement and analytical methods.

1.3.14.1.4. Following resolution, repeat the applicable test portion to verify that the Level 1 requirement is satisfied.

ERSTI-04-VY1-1409-000 Page 11 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.3.14.2. Level .2 Criteria is associated with design performance or plant parameters that are not expected to be exceeded while implementing this procedure and at that value are not immediately adverse to plant or equipment safety.

When a criterion is not met, place the test on HOLD and:

1.3.14.2.1. Hold at the most secure point and place the plant in a safe condition including reducing power if necessary.

1.3.14.2.2. Generate a CR and pursue resolution of the problem through investigating related adjustments as well as measurement and analytical methods.

1.3.14.2.3. Repeat the applicable test portion to verify that the Level 2 requirement is satisfied following the resolution unless the as-found condition is found to be satisfactory.

ERSTI-04-IMY1-1409-000 Page 12 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.3.14.3. Level 3: Criteria associated with plant surveillance acceptance criteria.

When criteria is not met:

Normal plant procedures will be followed if Level 3 Acceptance Criteria is exceeded.

1.3.14.4. Level 4: Criteria associated with plant operating procedures, for example, operator rounds, operating procedures, alarm response sheets, etc.

When criteria is not met:

Normal plant procedures will be followed if Level 4 Acceptance Criteria is exceeded.

1.3.15. Test Engineer - Per ENN-DC-1 17 a qualified individual for any organization, designated by the Testing Authority to perform the responsibilities of the Test Engineer. Qualifications for filling the Test Engineer function are in accordance with ENN-TQ-104.

1.3.16. Testing Authority - Per ENN-DC-l 17, the Testing Authority is the individual who owns the testing process. The Systern Engineering Manager is the Testing Authority.

ERSTI-04-Y 1-I1409-000 Page 13 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.4. Responsibilities The roles and responsibilities established to support this procedure are as follows:

1.4.1. Management Designee: A management person who holds an SRO license/certification, DCO qualified, a superintendent or higher level member of the plant staff or other individual that has been designated by the General Manager Plant Operations with responsibility for management oversight as defined in this procedure. He/she shall provide overall line management authority for the safe conduct of an infrequently performed test or evolution. The Management Designee does not replace any individual involved in the test or evolution, nor supervise the evolution.

The Management Designee's function is management oversight.

1.4.2. Shift Manager - The SM has the responsibility for the safe operation of the plant at all times. The SM's approval is required prior to performance of this test and has the authority to stop the test at any time. The SM's approval is also required to continue testing if a test was terminated.

1.4.3. Control Room Supervisor (CRS) provides direction to Licensed Operators and other on-shift Operations personnel involved in the performance of this test.

ERSTI-04-7Y1 -1409-000 Page 14 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.4.1. Principal IPTE Coordinator [PIPTEC] - is responsible for overall implementation of the procedure. His responsibilities are spelled out in AP 6100. The PIPTEC will maintain control of all test activities and seek assistance from support departments as necessary. The PIPTEC or their designees will be responsible for signing off steps as completed within this procedure. The PIPTEC have the following duties and responsibilities with respect to the activities being controlled by this procedure. The SM shall not be assigned as a PIPTEC.

Reports test status and significant issues to station management.

Coordinates the activities requiring completion by this procedure to assure they are completed in a safe and timely marner.

Responsible for assuring this procedure is updated and maintained current with work and testing activities controlled by this procedure.

Reviews the exceptions to this procedure and expedites the resolution if exceptions affect power ascension testing.

Authorizes the next step in power ascension testing if the test data results meet the acceptance criteria.

May add additional equipment performance monitoring data collection at any time during the performance of this procedure.

Assures that shift personnel are knowledgeable of test activities being controlled and performed by this procedure.

ERSTI-04-VYl-1409-000 Page 15 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1.4.2. Test Engineer - Per ENN-DC-1 17 a qualified individual for any organization, designated by the Testing Authority to perform the responsibilities of the Test Engineer. Qualifications for filling the Test Engineer function are in accordance with ENN-TQ-104. The Test Engineer will have the following duties and responsibilities with respect to the activities being controlled by this procedure.

The Test Engineer may assist in the development and/or presentation of technical aspects of this evolution.

Has administrative and physical control of this procedure.

Maintains a log.

Maintains technical control of this procedure and is authorized to make changes to the acceptance limits of the system and equipment following an engineering evaluation that justifies the change in accordance with ENN-DC-1 17 1.4.3. Operations Support Personnel (AO's) - Operations Control Room personnel and auxiliary operators will perform the necessary plant control manipulation to operate various valves, equipment, and systems.

1.4.4. Test Team [IPTE Team]: A team of individuals, led by the, Management Designee, will monitor extended or complex IPTEs. Oversight team members do not replace any individuals involved in the test or evolution.

The team's function is to provide additional oversight.

1.4.5. Responsible Engineers, in conjunction with the Test Engineer and Shift Manager, have authority to change system and equipment acceptance limits or predicted performance values following an engineering evaluation that justifies the change in accordance with ENN-DC-1 17.

ERSTI-04-VrYI-1409-000 Page 16 of 118

Power Ascension Testing for Extended Power Uprate Conditions

2.

References:

2.1. AP 0020 Control Of Temporary And Minor Modifications 2.2. AP 0052 Pre Job Briefing 2.3. AP 0503 Establishing And Posting Restricted Areas 2.4. AP 6100, Infrequently Perfonned Test or Evolutions 2.5. DP 0636 Collection and Digestion of Metal Samples 2.6. DP 0643 Filterable Solids 2.7. EN-AD-103 Document Control and Records Management Activities 2.8. EN-LI-102 Corrective Action Process 2.9. ENN-DC-1 17 Post Modification Testing and Special Test Instructions 2.10. ENN-IT-104 Software Quality Assurance Program 2.11. ENN-OP-104 Resolution of Equipment Operability Concerns Related to Degraded or Nonconforming Conditions 2.12. ER 04-0529 ""EPU Instrumentation Upgrade Non Outage" 2.13. GE EPU Final Task Reports:

2.13.1. VY-RPT-05-00041, "T1005: Startup Test Specifications" 2.13.2. VY-RPT-05-00065, "T0500: Neutron Monitoring System" 2.13.3. VY-RPT-05-00066, "T0504: Feedwater Control System" 2.13.4. VY-RPT 05-00067, "T0506: NSSS TS Instrument Setpoints" 2.13.5. VY-RPT-05-00104, 'T0316: NSSS Piping Flow Induced Vibration Evaluation" 2.14. GE SIL 467, Recirculation System Bi-stable Flow in Jet Pump BWRs 2.15. GEI 88578 "Overspeed Operation Preparatory Procedure for Cold Starts" ERSTI-04-VY 1-1409-000 Page 17 of 118

Power Ascension Testing for Extended Power Uprate Conditions 2.16. GEK 459371, "Recommendation for Reading and Recording Generator Resistance Temperature Detectors and Thermocouples" 2.17. GEK 75526A "Operator Action on High Temperature Alarms" 2.18. I&T 2003-004.01 FWH Level Control System Installation and Test procedure 2.19. Licensing Topical report, "Generic Evaluations for General Electric Boiling Water Reactor Extended Power Uprate," NEDC-32523P-A Class III, February 2000 (ELTR-2) 2.20. Licensing Topical report, "Generic Guidelines for General Electric Boiling Water Reactor Extended Power Uprate," NEDC-32424P-A Class III, February 1999 (ELTR-1) 2.21. MM 2004-002 "EPR Modification for EPU" 2.22. MM 2004-039 "NSSS/BOP Instrumentation Upgrades for EPU" 2.23. NF 102 Corporate Fuel Reliability 2.24. Nuclear Change ER 2004-1409, Extended Power Uprate 2.25. OP 2199 Hydrogen Water Chemistry System 2.26. OP 0105 Reactor Operations 2.27. OP 0631 Radiochemistry 2.28. OP 2172 Feedwater System 2.29. OP 2404 Determination And Implementation Of Rod Movement Sequences 2.30. OP 2429 Recirculation Flow System Baseline Data Collection and Instrument Calibration 2.31. OP 2457, PCIOMR Implementation 2.32. OP 2613, Sampling and Analysis of the Off Gas System 2.33. OP 4110 Reactor Recirc System Surveillance ERSTI-04-VY1 -1409-000 Page 18 of 118

Power Ascension Testing for Extended Power Uprate Conditions, 2.34. OP 4160 Turbine Generator surveillance 2.35. OP 4401 Core Thermal Hydraulics Limits Evaluation 2.36. OP 4612 Sampling and Treatment of the Reactor Water System 2.37. OP 4617 Calculation of Chemistry Controlled Setpoints 2.38. OP 5399 I/C Calibration Of Important Computer Analog Inputs 2.39. Original GE Startup Test Instructions, Spec. No. 22A2219 KV Rev.0 2.40. Original GE Startup Test Instructions, Spec. No. 22A2219 KV Rev.0 2.41. OT 3110 Positive Reactivity Insertion 2.42. OT 3113 Reactor Low Level 2.43. OT 3114 Reactor High Level 2.44. OT 3115 Reactor Pressure Transients 2.45. PP 7401, Fuel Reliability Program 2.46. Safety Analysis Report for Vermont Yankee Nuclear Power Station Constant Pressure Power Uprate NEDC-33090P, dated September 2003.

2.47. STP 2002-004, Pressure Regulator Dynamic Testing.

2.48. STP 2003-004 Power Ascension Test Procedure 2.49. STP-22, Original Plant Startup Testing for the Pressure Regulator.

2.50. STP-23, Original Plant Startup Testing for the Feedwater Flow Conlrol System 2.51. Technical Evaluation 2004-037, Benchmarking Feedwater FCV Performance for EPU.

2.52. VY EPU License Amendment Request, PC 263 2.53. VYDC 2000-027, Main Turbine EPR replacement.

2.54. VYDC 2001-002, Feedwater Level Controls Upgrade.

ERSTI-04-VY1 -1409-000 Page 19 of 118

Power Ascension Testing for Extended Power Uprate Conditions 2.55. VYDC 2002-007, Feedwater Control System Replacement - Phase 2.

2.56. VYDC 2003-003 "New Main Generator TC's and RTD's and the ERFIS Software Modification" 2.57. VYDC 2003-004 Feedwater Heater Level Control System 2.58. VYNPS Startup Test ERSTI-04-NY1 -1409-000 Page 20 of 118

Power Ascension Testing for Extended Power Uprate Conditions,

3. Apparatus/Test Equipment 3.1. Dryer Data Collection per TA 2005-0015, Additional Strain Gauge Installation 3.2. Feedwater Heater Performance per TM 2003-035 Feedwater Heater Performance 3.3. Flow Induced Vibration Equipment per TM 2003-022, FIV Instrumentation 3.4. Hand held vibration equipment 3.5. Any other monitoring equipment required based on System Engineering System Monitoring Requirements 3.6. Calibrated Pressurized Ion Chamber (PIC) 3.7. Other instrumentation and equipment as required ERSTI-04-V7Y1-1409-000 Page 21 of 118

Power Ascension Testing for Extended Power Uprate Conditions

4. Precautions and Limitations 4.1. Reactor power levels given in percent are a percentage of the Extended Power Uprate of 1912 MWth = 100.00% LPU.

4.2. System and equipment performance shall be closely monitored to assure that operating limits and test criteria are not exceeded. Condition reports shall be submitted as required. Any discrepancies noted are reported to the Test Engineer and the PIPTEC with an evaluation to determine plant impact: (discrepancy resolved or power ascension terminated and/or power reduction commenced).

Attach evaluations within Attachment 9 as discussed in Section 9.

4.3. If during power operation any of the following occurs, it may be indication of vessel internals damage and debris carry over. Notify the Shift Manager, the General Manager, Plant Operations, the Test Engineer and the PIPTEC immediately. (OE14300)

Unbalance of Main Steam Line steam flow indication -5 5% greater than baseline values

Unbalance RPV water level -3 inches between level instruments from different reference legs.

Sudden drop in steam dome pressure 2-3 psig.

Unexpected or unexplained step increase of moisture carryover.

4.4. Any pressure or level step changes at a power plateau shall be made first in the downward direction, then in the upward direction. This includes testing the EPR, the MPR, and the feedwater level control system.

4.5. IF during any pressure or level step changes, the system shows signs of becoming unstable or the acceptance limits are approached, THEN stabilize the condition, OTHERWISE exit the condition. The next larger step change shall not be performed until an acceptable response is achieved from the previous smaller steps. This may require repeating a previous step.

4.6. Reactor Engineering shall ensure the testing will avoid operation in the buffer and exclusion regions of the power to flow map.

ERSTI-04-VY 1- 1409-000 Page 22 of 118

Power Ascension Testing for Extended Power Uprate Conditions 4.7. IF the EPR is inoperable (the MPR in control) for a time period greater than two hours per occurrence, THEN initiate a CR per ENN-LI-102. Ensure an operability determination, per ENN-OP- 1 04, is completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.8. The Test Engineer with the assistance of the Test Team shall coordinate the review and evaluation of the data package for each step of this procedure for acceptance criteria compliance.

4.9. ALARA principles should be balanced with observing plant systems during power ascension system inspections.

4.10. Power levels tolerances are -19 MWth, + 0 MWth.

4.11. Intentional operation greater than the current plateau (1593 MWth, 1673 MWth, 1752 MWth, 1832 MWth and 1912 MWth) is not permitted. The average CTP level over any eight-hour period shall not exceed the current plateau power level.

It is permissible to inadvertently exceed current power plateau by as much as 2%

(nominal 1912 MWth) for as long as 15 minutes. Lesser power excursions are permitted for longer periods (i.e., 1% excess for 30 minutes, 1/2%/c for one hour, etc.) as long as the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months average does not exceed the current power plateau.

(NRC Letter SSINS-0200, dated 8/22/80).

4.12. After any change in plant power level above 1593 MWth by the steps in this procedure, an approximate 60-minute stabilization period shall occur prior to recording system and equipment performance data with the exception of dryer and FIV data. Following the stabilization period and during the data collection period the plant shall be maintained in as stable a condition as is possible (i.e., no backwashing and pre-coating condensate demineralizers, pump swap-over, etc) until data collection has been completed.

4.13. Record dryer data collection every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1(A-Y).

ERSTI-04-Y 1Y- 1409-000 Page 23 of 118

Power Ascension Testing for Extended Power Uprate Conditions

5. Termination Criteria 5.1. If an unexpected action results during performance of this procedure:

STOP, PLACE SYSTEM OR COMPONENT IN A SAFE CONDITION, AND NOTIFY THE SHIFT MANAGER, THE TEST ENG[NEER AND THE PIPTEC.

5.2. Terminate the IPTE upon the occurrence of:

5.2.1. Exceeding any Level 1 Criteria 5.2.2. Any specific termination/abort criterion defined in applicable procedures or attachments.

5.2.3. Any related event that causes an unexpected reactivity transient, such as that associated with reactor water level, pressure, core flow, temperature, or control rod position.

5.2.4. Any event which requires entering a Technical Specification Limiting Condition for Operation (LCO).

5.2.5. Any IPTE related event that is reportable or potentially reportable to the NRC, such as reactor scram, ECCS actuation, an uncontrolled radiation release or other Condition Report of noteworthy concern.

5.2.6. Any other condition which, in the determination of the PIPT EC, Management Designee, upper management or SM, requires Ihe IPTE to be terminated.

5.3. IF this test is TERMINATED), THEN record and document the exception on test deficiency log in accordance with ENN-DC-117, and generate a CR. Any CRs effecting operability must be reviewed by SM and the Management designee.

Notify the GMPO and 91-01 Coordinator (or equivalent).

ERSTI-04-TY1 -1409-000 Page 24 of 118

Power Ascension Testing for Extended Power Uprate Conditions 5.4. If the decision is made to restart or continue an IPTE which was terminated/aborted, the Management Designee and/or PIPTEC shall perform the following prior to proceeding with the test:

5.4.1. Obtain GMPO approval and review by OSRC (if required).

5.4.2. Obtain SM permission.

5.4.3. Ensure resumption will not have unacceptable impact on plant status, operating equipment, or the remainder of the evolution.

5.4.4. Verify prerequisites are met and conditions have not changed since entering the terminated/aborted condition. If conditions have changed, complete applicable steps on the original prerequisites. page or on additional pages and attach to the procedure.

5.4.5. Document the re-vefification of prerequisites and continuation in the Control Room Log.

5.4.6. Ensure the Operating crew has been re-briefed and has taken a Take Two to refocus on the task.

5.5. IF during the performance of this procedure, testing is stopped for whatever reason, THEN refer to Termination Criteria for actions to be taken PRIOR to resuming testing.

ERSTI-04-VY1 -1409-000 Page 25 of 118

Power Ascension Testing for Extended Power Uprate Conditions 5.6. If an unexpected event occurs at any time during system testing, the system shall be placed in a safe and stable mode using existing operating procedures. Testing activities shall be suspended and placed on HOLD until the event is understood and the SM and the PIPTEC has granted permission to resume testing. The test engineer shall document the decision making on test deficiency log, recording the resolution and approvals granted in accordance with ENN-DC-l 17. Submit a Condition Report per EN-LI-102. Some examples are;

If inadequate manpower is available on site or via telephone to ensure successful completion of the evolution.

To resolve concerns with the evolution or with personnel assigned to the evolution.

Upon loss of required communications.

If plant impacts or conflicts with other procedures are identified that are not addressed by the procedures governing the special evolution.

ERSTI-04-VTY1-1409-000 Page 26 of 118

Power Ascension Testing for Extended Power Uprate Conditions:

6. Prerequisites Verify the following items identified in this section have been implemented and are complete and/or are operable, as appropriate:

NOTE Prerequisites do not have to be completed in sequence up to step 6.17, Shift Manager's permission to commence license implementation for EPU. Steps prior to 6.17 can be signed off prior to the receipt of the license amendment.

The following modifications have been completed in accordance with design engineering requirements.

Applicable post modification testing has been scheduled or completed, based on plant conditions, and procedures revised as required.

Operations has accepted the modified system and there are NO exceptions which preclude power operation up to 1912 MWth.

Confirmation of the completion of a modification is initialed by the Test Engineer, another member of the Test Team, or the Responsible Engineer for the modification.

6.1. Minor Modifications: Responsible Engineer 6.1.1. MM 2003-017, Modify RHRSW A Motor Cooling Piping

/ I Initial Date Time 6.1.2. MM 2003-018, Modify RHRSW B Motor Cooling Piping

/ /

Initial Date Time ERSTI-04-tY1 - 1409-000 Page 27 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.2. Temporary Modifications/Alterations: Responsible Engineer 6.2.1. TM 2003-022, FIV Instrumentation (Vibration sensors)

/ /

Initial Date Time 6.2.2. TM 2003-035 Feedwater Heater Performance Monitoring.

/ l Initial Date Time 6.2.3. TA 2005-0015, Additional Strain Gauge Installation

/ I Initial Date Time 6.3. Technical Specification Changes 6.3.1. PC-263, EPU l l Initial Date Time 6.3.2. PC-262, AST l l Initial Date Time 6.4. VYDC completed and implemented: Responsible Engineer 6.4.1. VYDC 2003-020, Replacement 381 Breaker l l Initial Date Time 6.4.2. VYDC 2003-016, Alternate Source Term l l Initial Date Time ERSTI-04-VY1 -1409-000 Page 28 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.5. Nuclear Changes 6.5.1. ER 2004-0705, Cooling Tower Fans/Motors

/ I Initial Date Time 6.5.2. ER 2004-1298, LP Turbine 8th Stage Diaphragms Initial Date Time 6.5.3. ER 2004-1267, MS Low Point Sockolet Reinforcement

/ I Initial Date Time 6.5.4. ER 2004-0971, Main Transformer (GSU)

Differential Protection

/ I Initial Date Time 6.5.5. ER 2005-0731, Isokinetic Sample Probes l l Initial Date Time 6.5.6. ER 2005-0776, Feedwater Pump Trip l l Initial Date Time 6.5.7. ER 2004-0975, Generator CT Upgrade

/ /

Initial Date Time 6.5.8. ER 2004-1409, EPU

/ /

Initial Date Time ERSTI-04-VYI -1409-000 Page 29 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.5.9. ER 2004-0529, Setpoints and Scaling Changes Required by EPU (approval of document only, implementation is controlled by this procedure.)

l l Initial Date Time 6.5.10. ER 2006-1099, Reactor Recirculation Runback Termination Point Change I /

Initial Date Time 6.5.11. ER 2005-1002 Modification to Feedwater Level Control System to Support EPU

/ /

Initial Date Time ERSTI-04-Y 1-1409-000 Page 30 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.6. OPERATIONS EPU TRAINING (Training) 6.6.1. The required training to operate the plant under EPU conditions has been conducted. Classroom training includes plant design changes in support of EPU including setpoint changes, changes to parameters, procedures and system operation, all related Technical Specification changes, and this Power Ascension Special Test. Simulator training has provided Operators with a demonstration of transients that show the greatest change in plant response at EPU power levels compared to the original maximum power level.

I /

Initial Date Time NOTE This prerequisite does not pertain to any particular Just-in-Time training Operations Management chooses to conduct for Operations personnel performance of power ascension testing.

6.6.2. Evaluation Comments:

//

Initial Date Time ERSTI-04-VY1-1409-000 Page 31 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.7. EPU Project Action Items 6.7.1. Throughout the EPU Project, action items have been tracked on an internal Action Item List and via PCRS assignments. These tracking mechanisms have been reviewed for items requiring completion prior to or during power ascension testing. The items requiring completion prior to exceeding 1593 MWth have been completed or will be completed as controlled by this procedure. (EPU)

Comments:

/ I Initial Date Time 6.7.2. Steam Dryer Action Items (EPU)

The commitments and planned actions specified in the EPU license amendment pertaining to the steam dryer required prior to power ascension have been completed. This step shall be completed prior to increasing power above 1593 MWth.

Comments:

Verified By:

Licensing Manager/Date Verified By:

EPU Project Manager/Date ERSTI-04-)TY1-1409-000 Page 32 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.7.3. Technical Specifications and TRM (OPS)

LCO Tracking Database has been reviewed and evaluated for any impact on the ability of the plant to support power ascension testing and has been found acceptable for power increase. Exceptions requiring action shall be listed below by exception number and shall be annotated in Test Deficiency Log.

Comments:

I /

Initial Date Time 6.8. LOG REVIEWS 6.8.1. TEMPORARY ALTERATION (MODIFICATIONS) LOG REVIEW (System Engineering) 6.8.1.1. The Temporary Alteration (Modifications) Log has been reviewed and all installed Temp Alts have been evaluated for their impact on this Power Ascension Test and have been found acceptable. Exceptions requiring action shall be listed in Test Deficiency Log.

Comments:

l l Initial Date Time ERSTI-04-VY 1-1409-000 Page 33 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.8.2. Operability Evaluation/ODMI Log Review: (OPS) 6.8.2.1. All Operability Evaluations/ODMIs that have EP'U constraints been evaluated for their impact on Power Ascension and have been found acceptable. Exceptions requiring action shall be listed in Test Deficiency Log.

Comments:

I /

Initial Date Time ERSTI-04-V\Y 1-1409-000 Page 34 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.9. PROCEDURE REVIEW AND ISSUANCE 6.9.1. The EPU Project has resulted in the completion of many modifications, Technical Specification revisions and system operating parameter changes. These changes affect many Site procedures. This prerequisite requires the responsible Department Head review the procedures under their control and verify that:

They have reviewed the procedures under their control for minor modifications, design changes, temp modifications, and license amendments.

Have evaluated the impact of the differences between the Final License amendment and the proposed License amendment on various procedure changes.

Training of personnel within their department has been completed as required by the revised procedures.

Procedures required for power ascension have been issued and distributed for plant usage.

By signing iFor their respective department procedures, the responsible department head verifies that plant procedures assigned to the department required for power ascension have been revised accordingly.

Functional Group Dept Head/ Signature Exceptionsl Date/Time Maintenance Operations Chemistry Radiation Protection Engineering Training Emergency Preparedness Reactor Engineering General Manager Licensing Safety Quality Assurance CA&A

' Record exceptions on the Test Deficiency Log and enter the log number on this page.

ERSTI-04-VY1 -1409-000 Page 35 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.10. SER Review 6.10.1. The NRC Final Safety Evaluation Report and License Amendment have been reviewed against the License Amendment Request and any differences have been evaluated for their affect on;

. Plant Operating Procedures 0 Plant Processes and Programs 0 This Power Ascension Test Procedure This evaluation has been completed and there are no additional changes to the documents listed above prior to the start of Power Ascension Testing as performed by this procedure.

Evaluation Comments Comments:

Verified By:

Licensing Manager/Date Verified By:

EPU Project Manager/Date ERSTI-04-XNY1-1409-000 Page 36 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.11. EQUIPMENT CLEARANCE ORDERS AND EQUIPMENT STATUS TAGS (OPS) 6.1 1.1. The equipment that is Out-of-Service that can affect the ability of the plant to support power ascension testing has had its plant impact reviewed and evaluated and found acceptable for power increase. Exceptions requiring action shall be listed below by exception number and shall be annotated in Test Deficiency Log in accordance with ENN-DC-1 17.

6.11.2. Review Comments:

l l Initial Date Time ERSTI-04-IY 1-1409-000 Page 37 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.12. Verify the following Instrumentation Prerequisites completed:

6.12.1. ERFIS is available for monitoring test parameters (RE) including:

6.12.1.1. VYOPF 0452.01 2005-037 ERFIS Condensate and Feedwater Pump and Motor Bearing Temperature Setpoint Increase for EPU.

/ /

Initial Date Time 6.12.1.2. VYOPF 0452.01 2005-021, ERFIS F005, C008 Condensate Flow Re-range for EPU

/ /

Initial Date Time 6.12.1.3. VYOPF 0452.01 2005-025, ERFIS Miscellaneous EPU Change l l Initial Date Time 6.12.2. TA 2005-0015 Strain Gauges (DE)

/ I Initial Date Time 6.12.3. TM 2003-0035, Feedwater Heater Performance Monitoring (DE) l l Initial Date Time 6.12.4. TM 2003-022, FIV Monitoring (DE)

/ I Initial Date Time ERSTI-04-IY1 -1409-000 Page 38 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.12.5. ER 04-529, EPU Instrument Changes: (I&C) 6.12.5.1. 2005E**060 Condensate Pump Motor Amp Control Room Indication Amber Band (Optional) l /

Initial Date Time 6.12.5.2. 2005C-005 Condensate Pump Discharge Pressure Control Room Pressure Indication Green Band (Optional)

I /

Initial Date Time 6.12.5.3. 2004C-023 PT-6-56 Main Turbine Bowl Pressure Transmitter

,' /

Initial Date Time 6.12.5.4. Calibration of FS-6-95 Steam Leak Detection

/

Initial Date Time 6.12.5.5. Calibration Data Sheet for FT-102 1 and Fl- 102-9 Condensate flow input to Oxygen Injection System Initial Date Time ERSTI-04-VY1 -Y1409-000 Page39 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.13. Administrative Controls:

The signature below signifies that power ascension above 1593 MWth may commence with all issues resolved or otherwise addressed.

6.13.1. Licensing Manager Signature / Date / Time 6.13.2. EPU Manager l l Signature / Date / Time 6.13.3. Engineering Director Signature / Date / Tirme 6.13.4. Operations Manager l l Signature / Date / Time 6.13.5. Reactor Engineering Superintendent l l Signature / Date / Time 6.13.6. CA&A Manager

/. .

Signature / Date / Time 6.13.7. Quality Assurance Manager

/ l Signature / Date / Time 6.13.8. Maintenance Manager l l Signature / Date / Time ERSTI-04-VlY1-1409-000 Page 40 of 118

w Power Ascension Testing for Extended Power Uprate Conditions 6.13.9. Chemistry Manager

/ / _

Signature / Date / Time 6.13.10. RP Manager

/ /

Signature / Date / Timre 6.14. All test team members have read and understood:

6.14.1. ERSTI-04-VYl-14C,9-000, Power Ascension Test Procedure for Extended Power Conditions 1:593 to 1912 MWth 6.14.2. EN-DC-I 17 Post Modification Testing and Special Testing Instructions.

6.14.3. AP 6100 Infrequently Performed Tests or Evolutions

/ / _

Days Initial Date Time

/ /

Nights Initial Date Time ERSTI-04-IY1 -1409-000 Page 41 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.15. PRE-JOB BRIEFS:

6.15.1. A pre-job brief has been performed per AP 6100 for PACC personnel involved on day shift.

/ I Initial Date Time 6.15.2. A pre-job brief has been performed per AP 6100 for PACC personnel involved on night shift.

I /_

Initial Date Time 6.15.3. A pre-job brief has been performed per AP 6100 for day shift test team members.

/ I Initial Date Time 6.15.4. A pre-job brief has been performed per AP 6100 for night shift test team members.

/ /

Initial Date Time 6.15.5. A pre-job brief has been conducted per AP 6100 for Operating Crews I /

Initial Date Time ERSTI-04-/Y1 - 1409-000 Page 42 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.16. Shift Manager's Permission to start:

6.16.1. THE SM'S PERMISSION HAS BEEN GRANTED TO COMMENCE LICENSE IMPLEMENTATION FOR EXTENDED POWER UPRATE.

Shift Manager/Date /Time 6.17. OSRC recommends license implementation for Extended Power Uprate to the GMPO.

OSRC Review Meeting #: _- /- I Initial Date Time 6.18. The GMPO authorizes implementation of the:

6.18.1. The license change per PC 263 I I Initial Date Time 6.18.2. The remaining prerequisites (Step 6.21) listed in this procedure which will effectively raised authorized reactor power limit to 1912 MWth I /

Initial Date Time 6.19. Verify that new license has been implemented in the control room.

/ /

Initial Date Time ERSTI-04-NY1-1409-000 Page 43 of 118

Power Ascension Testing for Extended Power Uprate Conditions Ai'n Trn m-....

Power Ascension Testing for Extended Power Uprate Conditions, 6.21.3 Work orders that implement ER 2004-0529, Setpoints and Scaling Changes Required by EPU:

6.21.3.1 2005C-OOIAPRM Flow Bias Scram (A/M) l l Initial Date Time 6.21.3.2 2005C.*002 APRM Flow Bias Rod Block (A/M) l l Initial Date Time 6.21.3.3 2005C*.003 MSL High Flow M/S in RUN

/ /

Initial Date Time 6.21.3.4 2005C-004 MSL High Flow M/S Not in Run

/ /

Initial Date Time 6.21. Confirm the following documents are approved after the receipt of the NRC License Amendment.

6.21.1. Nuclear Change 04-1493

/ l_

Initial Date Time 6.21.2. TRM

/ l Initial Date Time 6.21.3. Input Assumption Source Document l l Initial Date Time 6.21.4. Calculation VYC-808 I /

Initial Date Time ERSTI-04-Y 1-1409-000 Page 45 of 118

Power Ascension Testing for Extended Power Uprate Conditions 6.21.5. Calculation VYC-2374 I /

Initial Date Time 6.21.6. Calculation VYC-2398

/ I Initial Date Time 6.21.7. Calculations VYC-2405 I

Initial Date Time 6.22. All prerequisites are complete and any exceptions are authorized and approved.

Verified By:

Test Engineer/Date/Time ERSTI-04-VY1 -1409-000 Page 46 of 118

Power Ascension Testing for Extended Power Uprate Conditions

7. Procedure NOTES

Power levels tolerances are -19 MWth, + 0 MWth.

Intentional operation greater than the current plateau (1593 MWth, 1673 MWth, 1752 MWth, 1832 MWth and 1912 MWth) is not permitted.

The average CTP level over any eight-hour period shall not exceed the current plateau power level. It is permissible to inadvertently exceed current power plateau by as much as 2% (nominal 1912 MWth) for as long as 15 minutes. Lesser power excursions are permitted for longer periods (i.e., 1% excess for 30 minutes, 1/2% for one hour, etc.) as long as the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months average does not exceed the current power plateau. (NRC Letter SSINS-0200, dated 8/22/80).

Data collection and evaluation at each power level may be performed in any order at that power level unless the section provides different direction.

IF during the performance of this procedure, testing is stopped for whatever reason, THEN refer to Termination/Hold Criteria, for actions to be taken PRIOR to resuming testing.

After any change in plant power level above 1593 MWth by the steps in this procedure, an approximate 60-minute stabilization period shall occur prior to recording system and equipment performance data with the exception of dryer data and FIV data. Following the stabilization period and during the data collection period the plant shall be maintained in as stable a condition as is possible (i.e., no backWashing and pre-coating condensate demineralizers, pump swap-over, etc.) until data collection has been completed.

The Test Engineer with the assistance of the Test Team shall coordinate the review and evaluation of the data package for each step of this procedure for acceptance criteria compliance.

ERSTI-04-VY 1-1409-000 Page 47 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.1. 1593 MWth With reactor power at 1574 MWth to 1593 MWth, and with three (3) Feedwater pumps running, perform the following:

7.1.1. Verify performed or perform dryer data collection per Attachment IA.

l l Initial Date Time 7.1.2. Verify performed or perform flow induced vibration measurement per Attachment 2A.

/ /

Initial Date Time 7.1.3. Verify performed or request RP to perform Radiation Surveys per Attachment 3.

/ /

Initial Date Time 7.1.4. Verify or request Operations to verify or place the "B" recombiner in service and the "A" recombiner in standby per OP 2150.

/ /

Initial Date Time 7.1.5. Verify performed or request RE to predict anticipated thermal limits for 1673 MWth per Attachment 4.

I /

Initial Date Time 7.1.6. Verify performed or request Chemistry to obtain baseline offgas samples per OP 2613, Sampling and Analysis of the Off Gas System. Attach per Section 9.0.

/ /

Initial Date Time ERSTI-04-VY1-1409-000 Page 48 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.1.7. Verify performed or request System Engineering to perform the System Engineering System Monitoring Plan baseline data at 1593 MWth and has been included within Attachment 9A.

/ /

Initial Date Time ERSTI-04-NY 1-1409-000 Page 49 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTES:

EPU power ascension testing above 1593 MWth will be conducted in approximately 40 MWth steps and 80 MWth plateaus.

The maximum power increase will not exceed a 80 MWth in a 24--hour period.

Steam Dryer Moisture Carryover Analysis needs to be performed at least once daily when reactor power is greater than 1593 MWth per Attachment 5.

7.1.8. If needed, raise reactor power and maintain 1593 MWth (1574 MWth to 1593 MWth).

/ I Initial Date Time 7.1.9. Authorization for Power Ascension:

7.1.9.1. General Manager, Plant Operations permission has been granted to exceed 1593 MWth.

I/

Initial Date Time 7.1.9.2. Shift Manager's permission has been granted to implement power ascension testing.

Initial Date Time ERSTI-04-IY1 -1409-000 Page 50 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.2. Increasing to 1633 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1633 MWth (1614 MWth to 1633 MWth) in accordance with OP 0105, Reactor Operations, as follows:

7.2.1. While raising reactor power:

7.2.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment 1B at 1609 MWth (1590 MWth to 1609 MWth).

Initial Date Time 7.2.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 1C at 1625 MWth (1606 M'%'th to 1625 MWth).

Initial Date Time 7.2.1.3. Perform dryer data collection per Attachment 1D after achieving 1633 MWth (1614 MWth to 1633 MWth).

,/

Initial Date Time ERSTI-04-V YI-1409-000 Page 51 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.2.2. Maintain reactor power (1614 MWth to 1633 MWth) for four hours while performing the following non intrusive activities:

7.2.2.1. Perform flow induced vibration measurement per Attachment 2B. (non intrusive)

I /

Initial Date Time 7.2.2.2. Request R]E to:

7.2.2.2.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/ /

Initial Date Time 7.2.2.2.2. Verify all inputs to the heat balance acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0. (non intrusive)

/ /

Initial Date Time 7.2.3. One hour after achieving 1633 MWth (1614 MWth to 1633 MWth), perform moisture carryover determination per Attachment 5A. (non intrusive)

I /

Initial Date Time ERSTI-04-rY1 -1409-000 Page 52 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.2.4. Four hours after achieving 1633 MWth (1614 MWth to 1633 MWth), perform Extraction Steam Reverse Current (RC() Valve Test in accordance with OP 4160 Section B, Extraction Steam Reverse Current Valve Test using VYOPF 4160.07. Hold each RCV test switch for 30 seconds or until a closed (green light) indication is observed. Record whether the valve indicated intermediate or closed.

Attach VYOPF 4160.07 per Section 9.0. (Intrusive)

/ I Initial Date Time 7.2.5. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

/ I Initial Date Time

/ /

Initial Date Time 7.2.6. Request Chemistry to verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617, Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented (non intrusive)

/ /

Initial Date Time ERSTI-04-VY 1-1409-000 Page 53 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.3. Increasing to 1673 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1673 MWth (1654 MWth to 1673 MWth) accordance with OP-0105, Reactor Operations, as follows:

7.3.1. While raising reactor -power:

7.3.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment IE at 1649 MWth (1630 MWth to 1649 MWth).

Initial Date Time 7.3.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment IF at 1665 MWth (1646 MWth to 1665 MWth).

Initial Date Time 7.3.1.3. Perform dryer data collection per Attachment 1G after achieving 1673 MWth (1654 MWth to 1673 MWth).

/ I Initial Date Time ERSTI-04-Y 1Y-1409-000 Page 54 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.1.4. Notify the test team to complete report preparation that evaluates dryer data (strain gauge results, evaluations, acceptance criteria, etc,) and makes a recommendation to OSRC to continue power ascension.

OSRC Review Meeting #: _ / /

Initial Date Time 7.3.2. Perform flow induced vibration measurement per Attachment 2C. (Non intrusive).

/ /

Initial Date Time 7.3.3. Maintain reactor power 1654 MWth to 1673 MWth for a total of four hours.

/ /

Initial Date Time 7.3.4. Once each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

7.3.4.1. Verify moisture carryover per Attachment 5B. (non intrusive)

/ /

Initial Date Time 7.3.4.2. Verify moisture carryover per Attachment 5C. (non intrusive)

/ /

Initial Date Time 7.3.4.3. Verify moisture carryover per Attachment 5D. (non intrusive)

/ /

Initial Date Time 7.3.4.4. Verify moisture carryover for per Attachment 5E. (non intrusive)

/ /

Initial Date Time ERSTI-04-VYI-1409-000 Page 55 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.5. Once the dryer data has been evaluated and approved by OSRC and the General Manager, Plant Operations, perform the following (non-intrusive):

7.3.5.1. For the transmission of small data files (i.e., < 5 MB), email directly to:

Rick Ennis at rxe(ianrc.gov Jim Shea at jjs(,nrc.gov Jim Devincentis at idevinc(,entergy.com Enrico Betti at ebetti(t),entergv.com Tom Scarbrough at tgs(a),nrc.gov John Wu at ciw(a-),nrc.gov Kamal Manoly at kam6i-nrc.gov

/I Initial Date Time 7.3.5.2. For the transmission of large data files (i.e., 5 MB or larger), upload to web folder at www.ibackup.com Account name: envydryer Password: Later and email the following persons the files have been uploaded on ibackup.com:

Rick Ennis at rxe(a),nrc.gov Jim Shea at jjs(i)nrc.gov Jim Devincentis at idevinc(a)entergy.com Enrico Betti at ebetti()enterg.com Tom ScarbFrough at tgs(a),nrc.gov John Wu at ciw(),nrc.gov Kamal Manoly at kam(),nrc.gov

/I Initial Date Time ERSTI-04-VrY1-1409-000 Page 56 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.5.3. Confirm receipt via telephone to NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the following numbers (start at top and proceed down list until a single contact is made. 'If Rick Ennis (or acting NRC PM) carmot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

//

Initial Date Time Contact Order

1. 301-415-1420 (Rick Ennis office)

2. 301-972-8225 (Rick Ennis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301-415-1430 (NRC secretary-request contact with Ennis or Shea)

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.3.5.4. Once confirmation has been received, record below the start and end time of the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock.

Start of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time Initial Date Time End of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time Initial Date Time ERSTI-04-TY1 -1409-000 Page 57 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.6. Cognizant Engineers to perform walkdowns per Engineering Monitoring Plans, including inspections where practicable based on ALARA and safety reasons, a review of ERFIS indications, local indications, control room indications, etc., for systems (components) affected by EPU. An evaluation needs to be completed for ANY discrepancy noted. Include this documentation within Attachment 9 to this procedure as discussed in Section 9. (non intrusive)

System Engineering Mechanical / I Initial Date Time System Engineering Electrical / /

Initial Date Time Programs and Component Engineering Plant Programs / /

Initial Date Time 7.3.7. Perform feedwater runout data per Attachment 6A and complete the analysis. (non intrusive)

/ /

Initial Date Time 7.3.8. Perform radiation surveys per Attachment 3. (non intrusive) l l Initial Date Time ERSTI-04-rY 1-1409-000 Page 58 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.9. Contact Chemistry to perform the following and include data within Attachment 1OA-1OD, as appropriate, to this procedure as discussed in Section 9.0. (non intrusive):

7.3.9.1. Monitor and record site boundary dose rates in accordance with Attachment 10.

/ /

Initial Date Time 7.3.9.2. Perform Reactor Coolant Iodine Activity in accordance with OP 0631, Radiochemistry.

/ /

Initial Date Time 7.3.9.3. Perform Reactor Coolant Chloride and Conductivity Analysis in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

/ I Initial Date Time 7.3.9.4. Perform Reactor Coolant Filterable Solids Analysis per DP 0643, Filterable Solids, Section C.

/ I Initial Date Time 7.3.9.5. Perform Reactor Coolant Isotopic (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months decay) in accordance with OP 0631, Radiochemistry, Appendix B.

/ I Initial Date Time 7.3.9.6. Perform Reactor Coolant 2 liter Metals Sample per DP 0636, Collection and Digestion of Metal Samples.

/ I Initial Date Time ERSTI-04-VY1 -1409-000 Page 59 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.9.7. Perform Feedwater Chemistry Analysis (02 and conductivity) in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

I Initial Date Time 7.3.9.8. Verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617 Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented.

//

Initial Date Time ERSTI-04-VrY1-1409-000 page 60 of 118

Power Ascension Testing for Extended Power Uprate Conditions Note:

VY is one of several GE-designed BWRs which experience recirc bi-stable flow patterns on a periodic basis. With no change in pump speed, these fluctuations can produce step-changes in drive flow, typically ranging from 0.1 milbs/hr to 0.35 mlbs/hr. Corresponding changes will also occur in jet pump flow, core flow, core power and electrical output:, ranging from 0.1% (with short-lived flow changes) to 2% or more (with longer-lived flow changes and/or at core flows greater than 100%).

These fluctuations have been observed at VY and at other facilities with a duration lasting a few seconds to about 1 minute, and at frequencies typically ranging from one to ten occurrences per hour, although up to 200 occurrences per hour have been observed. The magnitude, duration, and frequency of each flow pattern is random and is sensitive to small changes in influencing parameters such as recirc flow rate or pump speed. GE has performed plant-specific safety analyses and has concluded that the occurrence of recirc bi-stable flow is neither a safety concern nor an operability issue.

7.3.10. Operations to observe control room indications including ERFIS for bi-stable flow for several minutes. If bi-stable flow is observed, submit a condition report. (non intrusive)

Observed / not observed I /

Initial Date Time 7.3.11. Run 3-D Monicore Official Case. Perform Core Thermal Limits Verification in accordance with OP 4401. Attach per Section 9.0. (non intrusive)

/ /

Initial Date Time ERSTI-04-VYlI-1409-000 Page 61 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.12. Request RE to:

7.3.12.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

Initial Date Time 7.3.12.2. Verify all inputs to the heat balance are acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0.

(non intrusive)

/I Initial Date Time 7.3.12.3. Verify the ERFIS heat balance (C047) is +/- 3% to other alternate power indications by reviewing the APD display. Attach EFRIS APD screen per Section 9.0. (non intrusive)

Initial Date Time 7.3.12.4. Submit a 3-D Monicore case and review thermal limits at 1673 MWth.

Record and compare them against the predicted values on Attachment

4. Attach the 3-D Monicore case per Section 9.0. Predict anticipated thermal limits for 1752 MWth and record on Attachment 4. (non intrusive)

Initial Date Time ERSTI-04-VY1-1409-000 Page 62 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.12.5. Verify that the Process Computer is using jet pump based core flow and not the core flow based upon the drive flow-core flow relationship.

(non intrusive)

//

Initial Date Time 7.3.12.6. After a minimum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at this power plateau, save PCIOMR statepoint and compose the envelope per OP 2457, PCIOMR Implementation. (non intrusive)

/I Initial Date Time ERSTI-04-IY1 -1409-000 Page 63 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.13. Allowing no other concurrent intrusive activities, perform feedwater level control testing per Attachment 7A. (intrusive)

I /

Initial Date Time 7.3.14. Allowing no other concurrent intrusive activities, perform MHC demonstration per Attachment 8A. (intrusive)

/ /

Initial Date Time 7.3.15. Perform Recombiner Performance Monitoring per Attachment 11 A. (non intrusive)

I /

Initial Date Time 7.3.16. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

I /

Initial Date Time I /

Initial Date Time 7.3.17. Complete a report to be presented at OSRC used as a basis to recommend to the General Manager, Plant Operations, to continue the power ascension. (non intrusive)

OSRC Review Meeting #: I I Initial Date Time ERSTI-04-7Y1-1409-000 Page 64 of 18

Power Ascension Testing for Extended Power Uprate Conditions 7.3.18. Authorization for Power Ascension The results of testing and data collection performed at the last power level plateau have been analyzed and presented to the General Manager, Plant Operations, and approval to proceed has been obtained. (Non intrusive)

I /

Initial Date Time ERSTI-04-VY 1-1409-000 Page 65 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.19. After 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from the time NRC NRR received the dryer data and evaluation submittal and with no objections from NRC NRR, then call the NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the following numbers (start at top and proceed down list until a single contact is made) and inform the NRC that VY is continuing with the power ascension. (non intrusive) 7.3.19.1. If Rick Ennis (or acting NRC PM) cannot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

Initial Date Time Contact Order

1. 301-415-1420 (Rick Ennis office)

2. 301-972-8225 (Rick Ennis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301-415-1430 (NRC secretary-request contact with Ennis or Shea)

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.3.19.2. Email the following individuals to inform them VY is continuing with the power ascension. Attach email per step 9.

Rick Ennis at rxe(d),nrc.gov Jim Shea at iis(d),nrc.gov Jim Devincentis at idevinc(6entergy.com Enrico Betti at ebetti(a),entergy.com Tom Scarbrough at tgs(Pinrc.gov John Wu at ciw()nrc.gov Kamal Manoly at kamr).nrc.gov Initial Date Time ERSTI-04-Y 1Y-1409-000 Page 66 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.3.19.3. Continue with the power ascension.

/ I Initial Date Time Licensing: /

(Print/Sign) (Date)

ERSTI-04-VY1-1409-000 Page 67 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.4. Increasing to 1712 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1712 MWth (1693 MWth to 1712 MWth) in accordance with OP 0105, Reactor Operations, as follows:

7.4.1. While raising reactor power:

7.4.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment 1H at 1689 MWth (1670 MWth to 1689 MWth).

/ _

Initial Date Time 7.4.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 1I at 1705 MWth (1686 MWth to 1705 MWth).

l l Initial Date Time 7.4.1.3. Perform dryer data collection per Attachment 1J after achieving 1712 MWth (1693 MWth to 1712 MWth).

/ l Initial Date Time ERSTI-04-rY1-1409-000 Page 68 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.4.2. Maintain reactor power 1712 MWth (1693 MWth to 1712 MWth) for four hours while performing the following non intrusive activities:

7.4.2.1. Perform flow induced vibration measurement per Attachment 2D. (non intrusive)

I /

Initial Date Time 7.4.2.2. Request RE to:

7.4.2.2.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/ I Initial Date Time 7.4.2.2.2. Verify all inputs to the heat balance acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0. (non intrusive)

Initial Date Time 7.4.3. One hour after achieving 1712 MWth (1693 MWth to 1712 MWth), -perform moisture carryover determination per Attachment 5F. (non intrusive)

/ I Initial Date Time ERSTI-04-7YI -1409-000 Page 69 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.4.4. Four hours after achieving 1712 MWth (1693 MWth to 1712 MWth), perform Extraction Steam Reverse Current (RC) Valve Test in accordance with OP 4160 Section B, Extraction Steam Reverse Current Valve Test using VYOPF 4160.07. Hold each RCV test switch for 30 seconds or until a closed (green light) indication is observed. Record whether the valve indicated intermediate or closed.

Attach VYOPF 4160.07 per Section 9.0. (Intrusive)

I /

Initial Date Time 7.4.5. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

I l Initial Date Time l l Initial Date Time 7.4.6. Request Chemistry to verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617, Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented (non intrusive) l l Initial Date Time ERSTI-04-Y 1-1409-000 Page 70 of 118

NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Atlachment 1.

7.5. Increasing to 1752 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1752 MWth (1733 MWth to 1752 MWth) per hour in accordance with OP-0105, Reactor Operations, as follows:

7.5.1. While raising reactor power:

7.5.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment 1K at 1728 MWth (1709 MWth to 1728 MWth).

/ I Initial Date Time 7.5.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 1L at 1744 MWth (1725 MWth to 1744 MWth).

l l Initial Date Time 7.5.1.3. Perform dryer data collection per Attachment IM after achieving 1752 MWth (1733 MWth to 1752 MWth).

Initial Date Time ERSTI-04-'VY1 -1409-000 Page 71 of 118

Power Ascension Testing for Extended Power Uprate Conditions:

7.5.1.4. Notify the test team to complete report preparation that evaluates dryer data (strain gauge results, evaluations, acceptance criteria, etc,) and makes a recommendation to OSRC to continue power ascension.

OSRC Review Meeting #: iD I Initial Date Time 7.5.2. Perform flow induced vibration measurement per Attachment 2E. (Non intrusive).

/ I Initial Date Time 7.5.3. Maintain reactor power after achieving 1752 MWth (1733 MWth to 1752 MWth) for a total of four hours.

l l Initial Date Time ERSTI-04-XrY1-1409-000 Fage 72 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.4. Once each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

7.5.4.1. Verify moisture carryover per Attachment 5G. (non intrusive)

/ I Initial Date Time 7.5.4.2. Verify moisture carryover per Attachment 5H. (non intrusive) l l Initial Date Time 7.5.4.3. Verify moisture carryover per Attachment 51. (non intrusive) l l Initial Date Time 7.5.4.4. Verify moisture carryover for per Attachment 5J. (non intrusive) l l Initial Date Time ERSTI-04-VY 1-1409-000 Page 73 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.5. Once the dryer data has been evaluated and approved by OSRC and the General Manager, Plant Operations, perform the following (non-intrusive):

7.5.5.1. For the transmission of small data files (i.e., < 5 MB), email directly to:

Rick Ennis at rxeanrc.gov Jim Shea at jjs(&,nrc.gov Jim Devincentis at idevinc(&),entergy.com Enrico Betti at ebetti()entergy.com Tom Scarbrough at tgs(&,nrc.gov John Wu at ciw(&),nrc.gov Kamal Manoly at kam(&nrc.zov Initial Date Time 7.5.5.2. For the transmission of large data files (i.e., 5 MB or larger), upload to web folder at www.ibackup.com Account name: envydryer Password: Later and email the following persons the files have been uploaded on ibackup.com:

Rick Ennis at rxe(anrc.gov Jim Shea at iis(&nrc.gov Jim Devincentis at idevincc&entergv.com Enrico Betti at ebetti(i),entergy.com Tom Scarbrough at tgs(&)nrc.gov John Wu at ciw(),nrc.gov Kamal Manoly at kam(&nrc.gov

/

Initial Date Time ERSTI-04-VY1-1409-000 Page 74 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.5.3. Confirm receipt via telephone to NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the following numbers (start at top and proceed down list until a single contact is made. [f Rick Ennis (or acting NRC PM) cannot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

/I Initial Date Time Contact Order

1. 301-415-1420 (Rick Ennis office)

2. 301-972-8225 (Rick Ennis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301-415-1430 (NRC secretary-request contact with Ennis or Shea')

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.5.5.4. Once confirmation has been received, record below the start and end time of the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock.

Start of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time Initial Date Time End of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time

//

Initial Date Time ERSTI-04-VlY 1-1409-000 Page 75 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.6. Cognizant Engineers to perform walkdowns per the Engineering Monitoring Plans, including inspections where practicable based on ALARA and safety reasons, a review of ERFIS indications, local indications, control room indications, etc., for systems (components) affected by EPU. An evaluation needs to be completed for ANY discrepancy noted. Include this documentation within Attachment 9 to this procedure as discussed in Section 9. (non intrusive)

System Engineering Mechanical / I Initial Date Time System Engineering Electrical / I Initial Date Time Programs and Component Engineering Plant Programs / I Initial Date Time 7.5.7. Perform feedwater runout data per Attachment 6B and complete the analysis. (non intrusive) l l Initial Date Time 7.5.8. Perform radiation surveys per Attachment 3. (non intrusive)

/ /

Initial Date Time ERSTI-04-[Yl - 1409-000 Page 76 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.9. Contact Chemistry to perform the following and include data within Attachment IOA-IOD, as appropriate, to this procedure as discussed in Section 9.0. (non intrusive):

7.5.9.1. Monitor and record site boundary dose rates in accordance with Attachment 10.

Initial Date Time 7.5.9.2. Perform Reactor Coolant Iodine Activity in accordance with OP 0631, Radiochemistry.

l l Initial Date Time 7.5.9.3. Perform Reactor Coolant Chloride and Conductivity Analysis in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

l l Initial Date Time 7.5.9.4. Perform Reactor Coolant Filterable Solids Analysis per DP 0643, Filterable Solids, Section C.

l l Initial Date Time 7.5.9.5. Perform fReactor Coolant Isotopic (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months decay) in accordance with OP 0631, Radiochemistry, Appendix B.

l l Initial Date Time 7.5.9.6. Perform Reactor Coolant 2 liter Metals Sample per DP 0636, Collection and Digestion of Metal Samples.

/ l Initial Date Time ERSTI-04-XY1Y-1409-000 Page 77 of 118

Power Ascension Testing for Extended Power Uprate Conditions; 7.5.9.7. Perform Feedwater Chemistry Analysis (02 and conductivity) in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

Initial Date Time 7.5.9.8. Verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617 Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented.

l l Initial Date Time ERSTI-04-XY1- 1409-000 Page 78 of 118

Power Ascension Testing for Extended Power Uprate Conditions Nrote:

VY is one of several GE-designed BWRs which experience recirc bi-slable flow patterns on a periodic basis. With no change in pump speed, these fluctuations can produce step-changes in drive flow, typically ranging from 0.1 mlbs/hr to 0.35 mlbs/hr. Corresponding changes will also occur in jet pump flow, core flow, core power and electrical output, ranging from 0.1% (with short-lived flow changes) to 2% or more (with longer-lived flow changes and/or at core flows greater than 100%).

These fluctuations have been observed at VY and at other facilities with a duration lasting a few seconds to about 1 minute, and at frequencies typically ranging from one to ten occurrences per hour, although up to 200 occurrences per hour have been observed. The magnitude, duration, and frequency of each flow pattern is random and is sensitive to small changes in influencing parameters such as recire flow rate or pump speed. GE has performed plant-specific safety analyses and has concluded that the occurrence of recirc bi-stable flow is neither a safety concern nor an operability issue.

7.5.10. Operations observe control room indications including ERFIS for bi-stable flow for several minutes. If bi-stable flow is observed, submit a condition report. (non intrusive)

Observed / not observed

/ I Initial Date Time 7.5.11. Run 3-D Monicore Official Case. Perform Core Thermal Limits Verification in accordance with OP 4401. Attach per Section 9.0. (non intrusive)

/ /

Initial Date Time ERSTI-04-VY1Y-1409-000 Page 79 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.12. Request RE to:

7.5.12.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/I Initial Date Time 7.5.12.2. Verify all inputs to the heat balance are acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0.

(non intrusive)

/I Initial Date Time 7.5.12.3. Verify the ERFIS heat balance (C047) is +/- 3% to other alternate power indications by reviewing the APD display. Attach EFRIS APD screen per Section 9.0. (non intrusive)

/I Initial Date Time 7.5.12.4. Submit a 3-D Monicore case and review thermal limits at 1752 MWth.

Record and compare them against the predicted values on Attachment

4. Attach the 3-D Monicore case per Section 9.0. Predict anticipated thermal limits for 1832 MWth and record on Attachment 4. (non intrusive)

Initial Date Time ERSTI-04-VY1 -1409-000 Page 80of18

Power Ascension Testing for Extended Power Uprate Conditions 7.5.12.5. Verify that the Process Computer is using jet pump based core flow and not the core flow based upon the drive flow-core flow relationship.

(non intrusive)

Initial Date Time 7.5.12.6. After a minimum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at this power plateau, save PCIOMR statepoint and compose the envelope per OP 2457, PCIOMR Implementation. (non intrusive)

/ /

Initial Date Time 7.5.13. Allowing no other concurrent intrusive activities, perform feedwater level control testing per Attachment 7B. (intrasive)

Initial Date Time 7.5.14. Allowing no other concurrent intrusive activities, perform MHC demonstration per Attachment 8B. (intrusive)

/ /

Initial Date Time ERSTI-04-VrY1-1409-000 Page 81 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.15. Perform Recombiner Performance Monitoring per Attachment I IB. (non, intrusive)

I /

Initial Date Time 7.5.16. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

/ I Initial Date Time

/ /

Initial Date Time 7.5.17. Complete a report to be presented at OSRC used as a basis to recommend to the General Manager, Plant Operations, to continue the power ascension. (non intrusive)

OSRC Review Meeting #: /

I Initial Date Time 7.5.18. Authorization for Power Ascension The results of testing and data collection performed at the last power level plateau have been analyzed and presented to the General Manager, Plant Operations, and approval to proceed has been obtained. (Non intrusi've)

Initial Date Time ERSTI-04-N'Yl -1409-000 Page 82 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.19. After 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from the time NRC NRR received the dryer data and evaluation submittal and with no objections from NRC NRR, then call the NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the following numbers (start at top and proceed down list until a single contact is made) and inform the NRC that VY is continuing with the power ascension. (non intrusive) 7.5.19.1. If Rick Ennis (or acting NRC PM) cannot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

//

Initial Date Time Contact Order

1. 301-415-1420 (Rick E'nnis office)

2. 301-972-8225 (Rick E'nnis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301415-1430 (NRC secretary-request contact with Ennis or Shea)

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.5.19.2. Email the following individuals to inform them VY is continuing with the power ascension. Attach email per step 9.

Rick Ennis at rxe(d),nrc.gov Jim Shea at jis(i),nrc.gov Jim Devincentis at idevinc(aentergy.com Enrico Betti at ebetti(ientergy.com Tom Scarbrough at tgsamnrc.gov John Wu al: ciw(,nrc.gov Kamal Manoly at kamanrc.gov

//

Initial Date Time ERSTI-04-VY1-1409-000 Page 83 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.5.19.3. Continue with the power ascension.

l i Initial Date Time Licensing: I-(Print/Sign) (Date)

ERSTI-04-VY1 -1409-000 Page 84of118

Power Ascension Testing for Extended Power Uprate Conditions NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) an d within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.6. Increasing to 1792 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1792 MWth (1773 MWth to 1792 MWth) in accordance with OP 0105, Reactor Operations, as follows:

7.6.1. While raising reactor power:

7.6.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment IN at 1768 MWth (1749 MWth to 1768 MWth).

l l Initial Date Time 7.6.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 10 at 1784 MWth (1765 MWth to 1784 MWth).

l l Initial Date Time 7.6.1.3. Perform dryer data collection per Attachment IP after achieving 1792 MWth (1773 MWth to 1792 MWth).

l /

Initial Date Time ERSTI-04-NY1 -1409-000 Page 85 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.6.2. Maintain reactor power 1792 MWth (1773 MWth to 1792 MWth) for four hours while performing the following non intrusive activities:

7.6.2.1. Perform flow induced vibration measurement per Attachment 2F. (non intrusive)

/ I Initial Date Time 7.6.2.2. Request RE7 to:

7.6.2.2.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/ I Initial Date Time 7.6.2.2.2. Verify all inputs to the heat balance acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0. (non intrusive)

/ /

Initial Date Time 7.6.3. One hour after achieving 1792 MWth (1773 MWth to 1792 MWth), perform moisture carryover determination per Attachment 5K. (non intrusive)

/ /

Initial Date Time ERSTI-04-VY 1-1409-000 P'age 86 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.6.4. Four hours after achieving 1792 MWth (1773 MWth to 1792 MWth), perform Extraction Steam Reverse Current (RC) Valve Test in accordance with OP 4160 Section B, Extraction Steam Reverse Current Valve Test using VYOPF 4160.07. Hold each RCV test switch for 30 seconds or until a closed (green light) indication is observed. Record whether the valve indicated intermediate or closed.

Attach VYOPF 4160.07 per Section 9.0. (Intrusive) l l Initial Date Time 7.6.5. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

/ I Initial Date Time

/ I Initial Date Time 7.6.6. Request Chemistry to verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617, Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented (non intrusive)

/ I Initial Date Time ERSTI-04-VY1 -1409-000 Page 87 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTIE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 M'Wth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.7. Increasing to 1832 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1832 MWth (1813 MWth to 1832 MWth) in accordance with OP-0105, Reactor Operations, as follows:

7.7.1. While raising reactor power:

7.7.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment 1Q at 1808 MWth (1789 MWth to 1808 MWth).

/ I Initial Date Time 7.7.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 1R at 1824 MWth (1805 MWth to 1824 MWth).

/ /

Initial Date Time 7.7.1.3. Perform dryer data collection per Attachment IS after achieving 1832 MWth (1813 MWth to 1832 MWth).

/ /

Initial Date Time ERSTI-04-V7Y1-1409-000 Page 88 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.1.4. Notify the test team to complete report preparation that evaluates dryer data (strain gauge results, evaluations, acceptance criteria, etc,) and makes a recommendation to OSRC to continue power ascension.

OSRC Review Meeting #: I /

Initial Date Time 7.7.2. Perform flow induced vibration measurement per Attachment 2G. (Non intrusive).

/ I Initial Date Time 7.7.3. Maintain reactor power 1832 MWth (1813 MWth to 1832 MWth) for a total of four hours.

l l Initial Date Time 7.7.4. Once each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

7.7.4.1. Verify moisture carryover per Attachment 5L. (non intrusive) l l Initial Date Time 7.7.4.2. Verify moisture carryover per Attachment 5M. (non intrusive) l l Initial Date Time 7.7.4.3. Verify moisture carryover per Attachment 5N. (non intrusive)

I /

Initial Date Time 7.7.4.4. Verify moisture carryover for per Attachment 50. (non intrusive)

I /

Initial Date Time ERSTI-04-VY1 - 1409-000 Page 89 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.5. Once the dryer data has been evaluated and approved by OSRC and the General Manager, Plant Operations, perform the following (non-intrusive):

7.7.5.1. For the transmission of small data files (i.e., < 5 M:B), email directly to:

Rick Ennis at rxeO)nrc.gov Jim Shea at jjs0)nrc.gov Jim Devincentis at idevinc(ibentergy.com Enrico Betti at ebetti(&,entergy.com Tom Scarbrough at tgs(inrc.gov John Wu at ciw(,nrc.gov Kamal Manoly at kam(&nrc.gov Initial Date Time 7.7.5.2. For the transmission of large data files (i.e., 5 MB or larger), upload to web folder at www.ibackup.com Account name: envydryer Password: Later and email the following persons the files have been uploaded on ibackup.com:

Rick Ennis at rxe(&nrc.gov Jim Shea at iis(q-nrc.gov Jim Devincentis at idevinc(&entergy.com Enrico Betti at ebetti(),entergy.com Tom Scarbrough at tgsa),nrc.gov John Wu at ciw(),nrc.gov Kamal Marioly at kamr()nrc.gov I/

Initial Date Time ERSTI-04-IY 1-1409-000 Page 90 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.5.3. Confirm receipt via telephone to NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the

-following numbers (start at top and proceed down list until a single contact is made. '[f Rick Ennis (or acting NRC PM) carnot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

I/

Initial Date Time Contact Order

1. 301-415-1420 (Rick Ennis office)

2. 301-972-8225 (Rick Ennis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301-415-1430 (NRC secretary-request contact with Ennis or Shea)

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.7.5.4. Once confirmation has been received, record below the start and end time of the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock.

Start of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time

//

Initial Date Time End of 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock:

Date / Time I/

Initial Date Time ERSTI-04-VY1-1409-000 Page 91 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.6. Cognizant Engineers to perform walkdowns per the Engineering Monitoring Plans, including inspections where practicable based on ALARA and safety reasons, a review of ERFIS indications, local indications, control room indications, etc., for systems (components) affected by EPU. An evaluation needs to be completed for ANY discrepancy noted. Include this documentation within Attachment 9 to this procedure as discussed in Section 9. (non intrusive)

System Engineering Mechanical / /

Initial Date Time System Engineering Electrical / I Initial Date Time Programs and Component Engineering Plant Programs / I Initial Date Time 7.7.7. Perform feedwater runout data per Attachment 6C and complete the analysis. (non intrusive)

/ I Initial Date Time 7.7.8. Perform radiation surveys per Attachment 3. (non intrusive)

/ /

Initial Date Time ERSTI-04-NYI-1409-000 Page 92 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.9. Contact Chemistry to perform the following and include data within Attachment lOA-lOD, as appropriate, to this procedure as discussed in Section 9.0. (non intrusive):

7.7.9.1. Monitor and record site boundary dose rates in accordance with Attachment 10.

/ /

Initial Date Time 7.7.9.2. Perform Reactor Coolant Iodine Activity in accordance with OP 0631, Radiochemistry.

I /

Initial Date Time 7.7.9.3. Perform Reactor Coolant Chloride and Conductivity Analysis in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

/ / -

Initial Date Time 7.7.9.4. Perform Reactor Coolant Filterable Solids Analysis per DP 0643, Filterable Solids, Section C.

I /

Initial Date Time 7.7.9.5. Perform Reactor Coolant Isotopic (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months decay) in accordance with OP 0631, Radiochemistry, Appendix B.

l l Initial Date Time 7.7.9.6. Perform Reactor Coolant 2 liter Metals Sample per DP 0636, Collection and Digestion of Metal Samples.

I /

Initial Date Time ERSTI-04-NY1 -1409-000 Page 93 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.9.7. Perform Feedwater Chemistry Analysis (02 and conductivity) in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

Initial Date Time 7.7.9.8. Verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617 Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented.

/ /

Initial Date Time ERSTI-04-VY1-1409-000 Page 94 of 18

Power Ascension Testing for Extended Power Uprate Conditions Note:

VY is one of several GE-designed BWRs which experience recirc bi-stable flow patterns on a periodic basis. With no change in pump speed, these fluctuations can produce step-changes in drive flow, typically ranging from 0.1 m lbs/hr to 0.35 mlbs/hr. Corresponding changes will also occur in jet pump flow, core flow, core power and electrical output, ranging from 0.1% (with short-lived flow changes) to 2% or more (with longer-lived flow changes and/or at core flows greater than 100%).

These fluctuations have been observed at VY and at other facilities with a duration lasting a few seconds to about 1 minute, and at frequencies typically ranging from one to ten occurrences per hour, although up to 200 occurrences per hour have been observed. The magnitude, duration, and frequency of each flow pattern is random and is sensitive to small changes in influencing parameters such as recirc flow rate or pump speed. GE has performed plant-specific safety analyses and has concluded that the occurrence of recirc bi-stable flow is neither a safety concern nor an operability issue.

7.7.10. Operations observe control room indications including ERFIS for bi-stable flow for several minutes. If bi-stable flow is observed, submit a condition report. (non intrusive)

Observed / not observed

/ /

Initial Date Time 7.7.11. Run 3-D Monicore Official Case. Perform Core Thermal Limits Verification in accordance with OP 4401. Attach per Section 9.0. (non intrusive) i /

Initial Date Time ERSTI-04-XY1-1409-000 Page 95 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.12. Request RE to:

7.7.12.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/I Initial Date Time 7.7.12.2. Verify all inputs to the heat balance are acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0.

(non intrusive)

Initial Date Time 7.7.12.3. Verify the ERFIS heat balance (C047) is +/- 3% to other alternate power indications by reviewing the APD display. Attach EFRIS APD screen per Section 9.0. (non intrusive)

/I Initial Date Time 7.7.12.4. Submit a 3-D Monicore case and review thermal limits at 1832 MWth.

Record and compare them against the predicted values on Attachment

4. Attach the 3-D Monicore case per Section 9.0. Predict anticipated thermal limits for 1912 MWth and record on Attachment 4. (non intrusive)

//

Initial Date Time ERSTI-04-VY1 -1409-000 Page 96 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.12.5. Verify that the Process Computer is using jet pump based core flow and not the core flow based upon the drive flow-core flow relationship.

(non intrusive)

Initial Date Time 7.7.12.6. After a minimum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at this power plateau, save PCIOMR statepoint and compose the envelope per OP 2457, PCIOMR Implementation. (non intrusive)

/ I Initial Date Time ERSTI-04-NY1-1409-000 Page 97 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.13. Allowing no other concurrent intrusive activities, perform feedwater level control testing per Attachment 7C. (intrusive)

/ l Initial Date Time 7.7.14. Allowing no other concurrent intrusive activities, perform MHC demonstration per Attachment 8C. (intrusive) l l Initial Date Time 7.7.15. Perform Recombiner Performance Monitoring per Attachment IC. (non intrusive) l l Initial Date Time 7.7.16. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

I l Initial Date Time I /

Initial Date Time 7.7.17. Complete a report to be presented at OSRC used as a basis to recommend to the General Manager, Plant Operations, to continue the power ascension. (non intrusive)

OSRC Review Meeting #: I /

Initial Date Time ERSTI-04-[Y 1-1409-000 Page 98 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.18. Authorization for Power Ascension The results of testing and data collection performed at the last power level plateau have been analyzed and presented to the General Manager, Plant Operations, and approval to proceed has been obtained. (Non intrusive) l l Initial Date Time ERSTI-04-TY 1-1409-000 Page 99 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.19. After 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from the time NRC NRR received the dryer data and evaluation submittal and with no objections from NRC NRR, then call the NRC Project Manager Rick Ennis (or acting NRC Project Manager) at one of the following numbers (start at top and proceed down list until a single contact is made) and inform the NRC that VY is continuing with the power ascension. (non intrusive) 7.7.19.1. If Rick Ennis (or acting NRC PM) cannot immediately confirm receipt, ask for call back. Date stamp or other positive acknowledgment of NRC receipt.

/I Initial Date Time Contact Order

1. 301-415-1420 (Rick Ennis office)

2. 301-972-8225 (Rick Ennis home)

3. 301-814-5965 (Rick Ennis cellular phone)

4. 301-415-1388 (Jim Shea office)

5. 609-220-0306 (Jim Shea cellular phone)

6. 301-415-0560 (Darrell Roberts office)

7. 301-385-3326 (Darrell Roberts cellular phone)

8. 301-415-1430 (NRC secretary-request contact with Ennis or Shea)

9. 301-415-0550 (NRC Operations Center-request contact Ennis or Shea)

10. 301-816-5100 (NRC Operations Center-request contact Ennis or Shea) 7.7.19.2. Email the following individuals to inform them VY is continuing with the power ascension. Attach email per step 9.

Rick Ennis at rxe(inrc.gov Jim Shea at iis(a),nrc.gov Jim Devincentis at idevinc(aentergy.com Enrico Betti at ebetti(aentergy.com Tom Scarbrough at tgsd),nrc.gov John Wu at ciw(anrc.gov Kamal Manoly at kam(a)nrc.gov Initial Date Time ERSTI-04-TY1 -1409-000 Page 100 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.7.19.3. Continue with the power ascension.

il Initial Date Time Licensing: _

(Print/Sign) (Date)

ERSTI-04-1Y1- -1409-000 Page 101 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOT]_:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 M'Wth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.8. Increasing to 1872 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1872 MWth (1853 MWth to 1872 MWth) in accordance with OP 0105, Reactor Operations, as follows:

7.8.1. While raising reactor power:

7.8.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment IT at 1848 MWth (1829 MWth to 1848 MWth).

/ /

Initial Date Time 7.8.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment 1U at 1864 MWth (1845 MWth to 1864 MWth).

/ /

Initial Date Time 7.8.1.3. Perform dryer data collection per Attachment 1V after achieving 1872 MWth (1853 MWth to 1872 MWth).

/ /

Initial Date Time ERSTI-04-VY1 -1409-000 Page 102 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.8.2. Maintain reactor power 1872 MWth (1853 MWth to 1872 MWth) for four hours while performing the following non intrusive activities:

7.8.2.1. Perform flow induced vibration measurement per Attachment 2H. (non intrusive) l l Initial Date Time 7.8.2.2. Request R]E to:

7.8.2.2.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

/ I Initial Date Time 7.8.2.2.2. Verify all inputs to the heat balance acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0. (non intrusive)

/ /

Initial Date Time 7.8.3. One hour after achieving 1872 MWth (1853 MWth to 1872 MWth), perform moisture carryover determination per Attachment 5P. (non intrusive)

/ I Initial Date Time ERSTI-04-TY 1-1409-000 Page 103 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.8.4. Four hours after achieving 1872 MWth (1853 MWth to 1872 MWth), perform Extraction Steam Reverse Current (RC) Valve Test in accordance with OP 4160 Section B, Extraction Steam Reverse Current Valve Test using VYOPF 4160.07. Hold each RCV test switch for 30 seconds or until a closed (green light) indication is observed. Record whether the valve indicated intermediate or closed.

Attach VYOPF 4160.07 per Section 9.0. (Intrusive) l l Initial Date Time 7.8.5. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

I /

Initial Date Time l l Initial Date Time 7.8.6. Request Chemistry to verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617, Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented (non intrusive)

/ I Initial Date Time ERSTI-04-VY1 -1409-000 Page 104 of 118

Power Ascension Testing for Extended Power Uprate Conditions NOTE:

Dryer data collection readings (strain gauge and accelerometer data) are to be taken and evaluated every hour during power ascension (16 MWth change in reactor power) and within one hour of achieving the next power plateau per Attachment 1.

Reactor Power will need to be held constant, (within -19 MWth, +0 MWth) for approximately 2 minutes before and 15 minutes during the dryer data collection per Attachment 1.

7.9. Increasing to 1912 MWth Allowing no other concurrent intrusive activities, raise reactor power by 40 MWth to 1912 MWth (1893 MWth to 1912 MWth) in accordance with OP-0105, Reactor Operations, as follows:

7.9.1. While raising reactor power:

7.9.1.1. Perform dryer data collection after the first 16 MWth change in reactor power per Attachment 1W at 1888 MWth (1869 MWth to 1888 MWth).

l l Initial Date Time 7.9.1.2. Perform dryer data collection after the second 16 MWth change in reactor power per Attachment IX at 1904 MWth (1885 MWth to 1904 MWth).

l l Initial Date Time 7.9.1.3. Perform dryer data collection per Attachment 1Y after achieving 1912 MWth (1893 MWth to 1912 MWth).

/ /

Initial Date Time ERSTI-04-NY1-1409-000 Page 105 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.1.4. Notify the test team to complete report preparation that evaluates dryer data (strain gauge results, evaluations, acceptance criteria, etc,) and makes a recommendation to OSRC to continue power ascension.

OSRC Review Meeting #:

Initial Date Time 7.9.2. Perform flow induced vibration measurement per Attachment 21. (Non intrusive).

I /

Initial Date Time 7.9.3. Maintain reactor power 1912 MWth (1893 MWth to 1912 MWth) for a total of four hours.

I /

Initial Date Time ERSTI-04-VY1-1409-000 Page 106 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.4. Once each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

7.9.4.1. Verify moisture carryover per Attachment SQ. (non intrusive) i I Initial Date Time 7.9.4.2. Verify moisture carryover per Attachment 5R. (non intrusive)

I l Initial Date Time 7.9.4.3. Verify moisture carryover per Attachment 5S. (non intrusive) l l Initial Date Time 7.9.4.4. Verify moisture carryover for per Attachment 5T. (non intrusive) l l Initial Date Time ERSTI-04-VY 1-1409-000 Page 107 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.5. Cognizant Engineers to perform walkdowns per the Engineering Monitoring Plans, including inspections where practicable based on ALARA and safety reasons, a review of ERFIS indications, local indications, control room indications, etc., for systems (components) affected by EPU. An evaluation needs to be completed for ANY discrepancy noted. Include this documentation within Attachment 9 to this procedure as discussed in Section 9. (non intrusive)

System Engineering Mechanical / I Initial Date Time System Engineering Electrical / /

Initial Date Time Programs and Component Engineering Plant Programs / I Initial Date Time 7.9.6. Perform feedwater runout data per Attachment 6D and complete the analysis. (non intrusive) l l Initial Date Time 7.9.7. Perform radiation surveys per Attachment 3. (non intrusive)

/ /_

Initial Date Time ERSTI-04-N'Y 1-1409-000 Page 108 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.8. Contact Chemistry to perform the following and include data within Attachment 1OA-1OD, as appropriate, to this procedure as discussed in Section 9.0. (non intrusive):

7.9.8.1. Monitor arid record site boundary dose rates in accordance with Attachment 10.

l l Initial Date Time 7.9.8.2. Perform Reactor Coolant Iodine Activity in accordance with OP 0631, Radiochemistry.

/ I Initial Date Time 7.9.8.3. Perform Reactor Coolant Chloride and Conductivity Analysis in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

/ /

Initial Date Time 7.9.8.4. Perform Reactor Coolant Filterable Solids Analysis per DP 0643, Filterable Solids, Section C.

//

Initial Date Time 7.9.8.5. Perform Reactor Coolant Isotopic (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months decay) in accordance with OP 0631, Radiochemistry, Appendix B.

/ I Initial Date Time 7.9.8.6. Perform Reactor Coolant 2 liter Metals Sample per DP 0636, Collection and Digestion of Metal Samples.

/ /

Initial Date Time ERSTI-04-VrY1-1409-000 Page 109 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.8.7. Perform Feedwater Chemistry Analysis (02 and conductivity) in accordance with OP 4612, Sampling and Treatment of the Reactor Water System.

/ I Initial Date Time 7.9.8.8. Verify the Main Steam Line Radiation Monitor response is within the expected dose range per OP 4617 Calculation of Chemistry Controlling Setpoints or new Setpoint Change has been implemented.

l l Initial Date Time ERSTI-04-VY 1-1409-000 Page 10 ofll8

Power Ascension Testing for Extended Power Uprate Conditions Note:

VY is one of several GE-designed BWRs which experience recirc bi-stable flow patterns on a periodic basis. With no change in pump speed, these fluctuations can produce step-changes in drive f~low, typically ranging from 0.1 nilbs/hr to 0.35 mlbs/hr. Corresponding changes will also occur in jet pump flow, core flow, core power and electrical output, ranging from 0.1% (with short-lived flow changes) to 2% or more (with longer-lived flow changes and/or at care flows greater than 100%).

These fluctuations have been observed at VY and at other facilities with a duration lasting a few seconds to about 1 minute, and at frequencies typically ranging from one to ten occurrences per hour, although up to 200 occurrences per hour have been observed. The magnitude, duration, and frequency of each flow pattern is random and is sensitive to small changes in influencing parameters such as recirc flow rate or pump speed. GE has performed plant-specific safety analyses and has concluded that the occurrence of recirc bi-stable flow is neither a safety concern nor an operability issue.

7.9.9. Operations observe control room indications including ERFIS for bi-stable flow for several minutes. If bi-stable flow is observed, submit a condition report. (non intrusive)

Observed / not observed Initial Date Time 7.9.10. Run 3-D Monicore Official Case. Perform Core Thermal Limits Verification in accordance with OP 4401. Attach per Section 9.0. (non intrusive) l /

Initial Date Time ERSTI-04-IY 1-1409-000 Page 111 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.11. Request RE to:

7.9.11.1. Verify current reactor conditions are within acceptable values of the power-flow map (COLR figure 2.4-1). (non intrusive)

Initial Date Time 7.9.11.2. Verify all inputs to the heat balance are acceptable by reviewing ERFIS display HBI (Heat Balance Inputs).

Attach HBI screen per Section 9.0.

(non intrusive)

/ /

Initial Date Time 7.9.11.3. Verify the ERFIS heat balance (C047) is +/- 3% to other alternate power indications by reviewing the APD display. Attach EFRIS APD screen per Section 9.0. (non intrusive)

/ /

Initial Date Time 7.9.11.4. Submit a 3-D Monicore case and review thermal limits at 1912 MWth.

Record and compare them against the predicted values on Attachment

4. Attach the 3-D Monicore case per Section 9.0. (non intrusive) l l Initial Date Time ERSTI-04-VY1 -1409-000 Page 112 ofll8

Power Ascension Testing for Extended Power Uprate Conditions 7.9.11.5. Verify that the Process Computer is using jet pump based core flow and not the core flow based upon the drive flow-core flow relationship.

(non intrusive)

/ I Initial Date Time 7.9.11.6. After a minimum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at this power plateau, save PCIOMR statepoint and compose the envelope per OP 2457, PCIOMR Implementation. (non intrusive)

/ I Initial Date Time ERSTI-04-VY1- 1409-000 Page 113 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.9.12. Allowing no other concurrent intrusive activities, perform feedwater level control testing per Attachment 7D. (intrusive)

I/

Initial Date Time 7.9.13. Allowing no other concurrent intrusive activities, perform MHC demonstration per Attachment 8D. (intrusive)

I /

Initial Date Time 7.9.14. Perform Recombiner Performance Monitoring per Attachment lI D. (non intrusive)

/ /

Initial Date Time 7.9.15. Request Chemistry and RE to evaluate offgas levels for fuel integrity per PP 7401 Fuel Reliability Program and NF 102, Corporate Fuel Reliability.

Both parties to sign when complete. (non intrusive)

/ /

Initial Date Time

/ I Initial Date Time 7.9.16. Complete a report to be presented at OSRC used as a basis to recommend to the General Manager, Plant Operations, to remain at 1912 MWth. (non intrusive)

OSRC Review Meeting #: I I Initial Date Time ERSTI-04-NYl -1409-000 Page 114 of 118

Power Ascension Testing for Extended Power Uprate Conditions 7.10. Remaining at 1912 MWth 7.10.1. Authorization to remain at 1912 MWth.

The results of testing and data collection performed at the last power level plateau have been analyzed and presented to the General Manager, Plant Operations, and approval to remain at 1912 MWth been obtained. (Non intrusive) l l Initial Date Time GMPO: l (Print/Sign) (Date) 7.10.2. Prior to exceeding 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months of plant operation at the nominal full EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater. (intrusive) aD I Initial Date Time 7.10.3. Test Complete.

/ I Initial Date Time ERSTI-04-VIY1-1409-000 Page 115 of 118

Power Ascension Testing for Extended Power Uprate Conditions

8. Restoration 8.1. Perform an "End of Evolution" critique. Capture lessons learned Initial Date Time

9. Attachments Attachment Index Sheet Instructions:

This procedure requires that "data packages" and other performance monitoring data collection be attached to this procedure. Known attachments have been identified. For additional attachments, select the next sequential attachment number and record the attachment number in this index, with the document title, number of pages and associated procedure step and on the attached document.

Indicate the consecutive page number and total attachment pages at the bottom of each page.

Verified By:

Test Engineer/Date 1A Dryer Data Collection 1593 MWth 1B Dryer Data Collection 1609 MWth 1C Dryer Data Collection 1625 MWth ID Dryer Data Collection 1633 MWth 1E Dryer Data Collection 1649 MWth IF Dryer Data Collection 1665 MWth IG Dryer Data Collection 1673 MWth 1H Dryer Data Collection 1689 MWth 11 Dryer Data Collection 1705 MWth 1J Dryer Data Collection 1712 MWth 1K Dryer Data Collection 1728 MWth IL Dryer Data Collection 1744 MWth IM Dryer Data Collection 1752 MWth IN Dryer Data Collection 1768 MWtb 10 Dryer Data Collection 1784 MWtb 1P Dryer Data Collection 1792 MWth 1Q Dryer Data Collection 1808 MWth 1R Dryer Data Collection 1824 MWtl 1S Dryer Data Collection 1832 MWth ERSTI-04-7Y1 -1409-000 Page 116 of 118

Power Ascension Testing for Extended Power Uprate Conditions 1T Dryer Data Collection 1848 MWth 1U Dryer Data Collection 1864 MWth 1V Dryer Data Collection 1872 MWth 1W Dryer Data Collection 1888 MWth IX Dryer Data Collection 1904 MWth 1Y Dryer Data Collection 1912 MWth 2A Flow Induced Vibration Data 159-, MWth 2B Flow Induced Vibration Data 163-3 MWth 2C Flow Induced Vibration Data 1673 MWth 2D Flow Induced Vibration Data 1712 MWth 2E Flow Induced Vibration Data 1752 MWth 2F Flow Induced Vibration Data 1792 MWth 2G Flow Induced Vibration Data 1832 MWth S2H Flow Induced Vibration Data 1872 MWth 21 Flow Induced Vibration Data 1912 MWth 3 Radiation Surveys 4 Core Performance Data Sheet various MWth 5A Moisture Carryover 1633 MWth SB Moisture Carryover 1673 MWth 5C Moisture Carryover 1673 MWth 5D Moisture Carryover 1673 MWth 5E Moisture Carryover 1673 MWth 5F Moisture Carryover 1712 MWth 5G Moisture Carryover 1752 MWth 5H Moisture Carryover 1752 MWth 5I Moisture Carryover 1752 MWth 5J Moisture Carryover 1752 MWth 5K Moisture Carryover 1792 MWth 5L Moisture Carryover 1832 MWth 5M Moisture Carryover 1832 MWth 5N Moisture Carryover 1832 MWth 50 Moisture Carryover 1832 MWth 5P Moisture Carryover 1872 MWth 5Q Moisture Carryover 1912 MWth 5R Moisture Carryover 1912 MWth 5S Moisture Carryover 1912 MWth 5T Moisture Carryover 1912 MWth 6A Feedwater Runout Data Collection 1673 MWth 6B Feedwater Runout Data Collection 1752 MWth 6C Feedwater Runout Data Collection 1832 MWth 6D Feedwater Runout Data Collection 1912 MWth 7A Feedwater Level Changes 1673 MWth 7B Feedwater Level Changes 1752 M Wth ERSTI-04-VY1-1409-000 Page 117 of118

Power Ascension Testing for Extended Power Uprate Conditions 7C Feedwater Level Changes 1832 MWth 7D Feedwater Level Changes 1912 MWth 8A MHC Pressure Change 1673 MWth 8B MHC Pressure Change 1752 MWth 8C MHC Pressure Change 1832 MWth 8D MHC Pressure Change 1912 MWth 9A System Data 1593 MWth 9B System Data 1673 MWth 9C System Data 1572 MWth 9D System Data 1832 MWth 9E System Data 1912 MWth 10 Site Boundary Dose Measurements Various MWth lOAChemistry Data 1673 MWth lOB Chemistry Data 1572 MWth lOCChemistry Data 1832 MWth lODChemistry Data 1912 MWth 11 A Recombiner Performance Data 1673 MWth 1lB Recombiner Performance Data 1752 MWth 11 C Recombiner Performance Data 1832 MWth 1ID Recombiner Perfomrance Data 1912 MWth 12 Signature Identification Log 13 Test Deficiency Log 14 Performance Summary 15 ENN-LI-100 Process Applicability Determination 16 ENN-LI-101, 10.59 Screen 17 Risk Management Worksheet VYAPF 0172.02 ERSTI-04-XY1Y-1409-000 Page 118 of 118

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth)

NOTES:

Additional data collection may be performed at other power levels as directed by the Test Coordinator.

Strain gauges and accelerometers are assumed to be installed and tested via the work order process. The NI Data Acquisition Computer (NIDAC) and NI Hardware in the Reactor Building is on and operational. It is preferred that this system is controlled and monitored via a PC work station from outside the RCA.

Reactor Power, steam flow, and recirc flow needs to be held steady, (within -19 MWth,

+0 MWth) for approximately 2 minutes before and 15 minutes during the data collection at each test step. The data shall be recorded and evaluated within one hour of reaching each power step.

The strain gauge and accelerometer surveillance shall be performed hourly when increasing power above a level at which data was previously obtained. Operations shall identify windows during power ascension when steam flow is approximately steady state for the hourly data collection.

The process of increasing power from one step to the next level should be (but is not required) accomplished within one hour, including time to collect and evaluate data. If the step increase (including collection and evaluation of data) cannot be accomplished in one hour, then the collection and evaluation process should be repeated hourly until such time as the step increase is achieved.

For each data collection Strain Gauges are calibrated and nulled. Then there are two sets of data collected; each set approximately 40 seconds in length. The first set will include bridge excitation to produce/measure signal and noise. This will be followed by a second set with zero bridge excitation. This second set of data is used to identify recirc power electrical noise and AC power electrical noise from the strain signal.

The data is then processed and plotted by Steam Dryer Engineer within the hour.

Engineering shall provide plots, a written summary of data changes. Engineering shall assess the margin to the limit curve, assess the rate of change in sequential data, and provide a recommendation whether power ascension should continue. The MSL accelerometer data shall also be compared with strain gauge data. Engineering shall assess whether accelerometer data provides evidence that there are acoustic frequencies not identified by the SG data.

ERSTI-04-VY 1-1409-000 Attachment 1A Page 1 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 1.0 Test team to monitor the following ERFIS points:

B064 Main Steam Line Flow A

B065 Main Steam Line Flow B

B066 Main Steam Line Flow C

B067 Main Steam Line Flow D

B022 Total Steam Line Flow

C047 Core Thermal Power

M134 Recirc Pump A Speed

M135 Recirc Pump B Speed

3DMA015 Recirc Pump A Flow

3DMAO18 Recirc Pump B Flow

/ /

Initial Date Time 2.0 Confirm that NI Data Acquisition Computer (NIDAC) and NI Hardware on 252' elevation of the Reactor Building are on and operational.

l l Initial Date Time 3.0 Confirm that the Steam Dryer Engineer is prepared to acquire and process data

/ /

Initial Date Time 4.0 When the plant is at steady state power, confirm with the Steam Dryer Engineer to collect and evaluate strain gauge and accelerometer data.

l_ /

Initial Date Time ERSTI-04-VYF 1-1409-000 Attachment IA Page 2 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWthto 1593 MWth) 5.0 Confirm the with the reactor building data recorder station, and the Main Steam line strain gauge data collection, was successful. Record time and date below:

Time and date:

I /

Initial Date Time 6.0 Confirm with the Steam Dryer :Engineer the data evaluation has been completed within one hour of collecting the strain gauge and accelerometer data.

Record date and time of data evaluation completion.

Date and time evaluation complete: _

Determine time for evaluation: Initial Date Time 7.0 IF valid strain gauge and accelerometer data cannot be recorded and evaluated hourly or within one hour of initially reaching a 80 MWth power step from at least three of the four main steam lines, THEN an orderly power reduction shall be made to a lower power level at which data had previously been obtained. Any such power level reduction shall be completed within two hours of determining that valid data was not recorded.

Initial Date Time ERSTI-04-VY1-1409-000 Attachment 1A Page 3 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth)

8.0 Evaluation

8.1 IF the conditions of Table I can not be met, 8.1.1 THEN an orderly power reduction shall be made to a lower power level at which data had previously been obtained. Any such power level reduction shall be completed within two hours of determining that valid data was not recorded.

/ /

Initial Date Time Verified I)ate Time ERSTI-04-VW(1 -1409-000 Attachment IA Page 4 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 8.2 If the Level 2 performance criteria is exceeded based on Table 2, THEN 8.2.1 Promptly suspend reactor power ascension until an engineering evaluation concludes that further power ascension is justified.

l l Initial Date Time

/ /

Verified I)ate Time 8.2.2 Initiate a condition report.

/_ /

Initial Date Time

/ I Verified I)ate Time 8.2.3 Evaluate the cause of any exceedance of the performance criteria.

/ /

Initial Date Time

/ /

Verified I)ate Time 8.2.4 Before resuming reactor power ascension, the steamn dryer performance data shall be reviewed as part of an engineering evaluation to assess whether further power ascension can be made without exceeding the Level 1 criteria.

/_ /

Initial Date Time

/ /

Verified I)ate Time 8.2.5 Obtain GMPO permission to continue the power ascension.

/ /

Initial Date Time

/ /

Verified I)ate Time ERSTI-04-V(1 -1409-000 Attachment 1A Page 5 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 8.3 If the Level 1 performance criteria is exceeded based on Table 2, THEN:

8.3.1 Promptly initiate a reactor power reduction to a previously acceptable power level (i.e.,

reduce power to a previous step level) within two hours, unless an engineering evaluation concludes that continued power operation or power ascension is acceptable.

l l Initial Date Time Verified I)ate Time 8.3.2 Initiate a condition report.

l l Initial Date Time I_ I_

Verified I)ate Time 8.3.3 Evaluate the cause of any exceedance of the performance criteria.

/ /

Initial Date Time l l Verified I)ate Time 8.3.4 If the results of the engineering evaluation support continued power operation, reduce further power ascension step and plateau levels to nominal increases of 20 MWth and 40 MWth respectively, for any additional power ascension.

Initial Date Time

/ I Verified I)ate Time ERSTI-04-VW(1-1409-000 Attachment 1A Page 6 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 8.3.5 Within 30 days, the transient pressure data shall be used to calculate the steam dryer fatigue usage to demonstrate that continued power operation is acceptable.

/ /

Initial Date Time

/_ /

Verified I)ate Time 8.3.6 Obtain GMPO permission to continue the power ascension.

/ /

Initial Date Time Verified I)ate Time ERSTI-04-VY 1-1409-000 Attachment 1A Page 7 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 8.4 IF any frequency peak from the MSL strain gage data exceeds the limit curve established by Entergy Nuclear Operations, hic. and submitted to the NRC staff prior to operation above OLTP, 8.4.1 THEN reduce reactor power to where the limit curve was not exceeded. Engineering shall resolve the uncertainties in the steam dryer analysis, document the continued structural integrity of thie 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.

l_ l Initial Date Time l l Verified I)ate Time 8.5 IF resonance frequencies are identified as increasing above nominal levels in proportion to strain gage instrumentation data, 8.5.1 THEN hold reactor power, and 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.

l l Initial Date Time l l Verified Date Time ERSTI-04-VY1 -1409-000 Attachment 1A Page 8 ofl2

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth) 8.6 IF the acoustic signals are identified that challenge the limit curve during power ascension above OLTP, 8.6.1 THEN Engineering to e-valuate dryer loads and re-establish the limit curve based on the new strain gage data, and shall perform a frequency-specific assessment of ACM uncertainty at the acoustic signal frequency.

/ I Initial Date Time I /

Verified I)ate Time 8.7 IF an engineering evaluation is required in accordance with the Steam Dryer Monitoring Plan, 8.7.1 THEN Entergy Nuclear Operations, Inc.

shall perform the structural analysis to address frequency uncertainties up to +/-

10% and assure that peak responses that fall within this uncertainty band are addressed.

I l_

Initial Date Time

/ /

Verified I)ate Time 8.8 If the Level 1 or Level 2 performance criteria are NOT exceeded based on Table 2, 8.8.1 THEN recommend to OSRC that power ascension testing should continue.

I I_

Initial Date Time I /_

Verified I)ate Time ERSTI-04-VY 1-1409-000 Attachment 1A Page 9 ofl2

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth)

Table 1 Parameter Surveillance Frequency

1. Main steam line pressure data 'Hourly when initially increasing power above a from strain gauges previously attained power level.

-AND-At least once at every 40 MWth power step above 1593 MWth (Note 1)

2. Main steam piping accelerometer At least once at every 40 MWth LPU power step data from accelerometers in above 1593 MWth (Note 1) drywell -AND-Within one hour after achieving every 40 MWth power step above 1593 MWth.

Notes to Table 1:

1. The strain gauge and accelerometer surveillance shall be performed hourly when increasing power above a level at which data was previously obtained. The surveillance of both the strain gauge data and accelerometer data is also required to be performed once at each 40 MWth power step above 1593 MWth and within one hour of achieving each 40 MWth step in power. If the surveillance is met at a given power level, additional surveillances do not need to be performed at that power level where data had previously been obtained.

If valid strain gauge data cannot be recorded hourly or within one hour of initially reaching a 40 MWth power step from at least three of the four main steam lines, an orderly power reduction shall be made to a lower power level at which data had previously been obtained. Any such power level reduction shall be completed within two hours of determining that valid data was not recorded.

ERSTI-04-V{1 -1409-000 Attachment 1A Page 10 of 12

Attachment IA Dryer I)ata Collection 1593 MWth (1574 MWth to 1593 MWth)

Table 2 Performance Criteria Not to be Exceeded Required Actions if Performance Criteria Exceeded and Required Completion Times Level 2: 1 Promptly suspend reactor power ascension until an engineering evaluation concludes that further power

Pressure data exceed Level 2 Spectral ascension is justified.

per VYC-3001.

2. Before resuming reactor power ascension, the steam dryer performance data shall be reviewed as part of an engineering evaluation to assess whether further power ascension can be made without exceeding the Level 1 criteria.

Level 1: 1. Promptly initiate a reactor power reduction and achieve a previously acceptable power level (i.e.,

Pressure data exceed Level 1 Spectra' reduce power to a previous step level) within two per VYC-3001. hours, unless an engineering evaluation concludes that continued power operation or power ascension is acceptable.

2. If the results of the engineering evaluation support continued power operation, reduce further power ascension step and plateau levels to nominal increases of 20 MWth and 40 MWth respectively, for any additional power ascension.

3. Within 30 days, the transient pressure data shall be used to calculate the steam dryer fatigue usage to demonstrate that continued power operation is acceptable.

1 The EPU spectra shall be determined and documented in an engineering calculation or report. Acceptable Level 2 spectra shall be based on maintaining < 80% of the ASME allowable alternating stress (Sa) value at

<1011 cycles (i.e., < 10.88 ksi). Acceptable Level 1 Spectra shall be based on maintaining the ASME Sa at

<1011 cycles (i.e., <13.6 ksi).

ERSTI-04-VYI-1409-000 Attachment 1A Page 11 of 12

Attachment 1A Dryer Data Collection 1593 MWth (1574 MWth to 1593 MWth)

Reactor power operation that results in Steam pressures that are less than the Level 2 performance criteria in Table 2 is representative of fully acceptable steam dryer performance.

ERSTI-04-VY 1-1409-000 Attachment IA Page 12 of 12

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1574 MWth to 1593 MWth)

DRYWELL AREA Accel No./Dir. Measured Acceptance Sat / Unsat Acceleration Ag) Criteria (g)

MSA1 N-S <0.545 MSA2 Vert <0.230 MSA3 E-W <0.326 MSB1 N-S <0.274 MSB2 E-W <0.160 MSB3 N-S <0.269 MSB4 Vert <0.133 MSB5 E-W <0.248 MSB6 N-S <0.259 MSB7 E-W <0.202 MSB8 N-S <0.271 MSB9 Vert <0.286 MSB1O E-W <0.263 MSC1 N-S <0.264 MSC2 Vert <0.193 MSC3 E-W <0.170 MSD1 N-S <0.271 MSD2 Vert <0.254 MSD3 E-W <0.193 MSD4 N-S <0.271 MSD5 E-W <0.293 FDWA1 N-S <0.123 FDWA2 Vert <0.184 FDWA3 E-W <0.068 FDWB1 N-S <0.172 FDWB2 Vert <0.198 FDWB3 E-W <0.084 FDWB4 N-S <0.184 FDWB5 E-W <0.185 FDWB6 N-S <0.162 FDWB7 E-W <0.144 ERSTI-04-VY1 -1409-000 Attachment 2A Page 1 of 6

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1:574 MWth to 1593 MWth)

HEATER BAY AREA Accel No./Dir. Measured Acceptance Sat / Unsat Acceleration_ (gCriteria (g)

MSHB1 N-S <0.057 MSHB2 E-W <0.047 MSHB3 N-S <0.048 MSHB4 E-W <0.058 FDWHB1 N-S <0.103 FDWHB2 Vert <0.162 FDWHB3 E-W <0.076 Performed by:

Sign/Date (Design Engineering)

Verified by: _

Sign/Date (Design Engineering)

Note: Any UNSAT indication requires a Condition Report and an Engineering Evaluation. Request Operations to lower reactor power to the last tes.ted power level.

ERSTI-04-VY 1-1409-000 Attachment 2A Page 2 of 6

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1574 MWth to 1593 MWth)

Turbine Building Branch Piping Vibration Acceptance Criteria Valve(s) ID# Measured Measured Measured SRSS ( Accptance Sat Displacement Displacement displacement Criteria Unsat mils (2) N-S mils (R) E-W mils (R)mils

-Vertical V64-63B & V64-124 <34 V64-63A & V64-120 <28 V66-12E <44 V64-127 <6 V63-812A & B <27 V63-814A & B <26 V63-808C, D <15 V64-16A <4 V64-16B <4 V64-16C <4 SRSS = SQRT [(N-S mils) 2 + (E-W) 2 + (vertical 2 )]

Note: Any UNSAT indication requires a Condition Report and an Engineering Evaluation. Request Operations to lower reactor power to the last tested power level.

Performed by:

Sign/Date (Design Engineering) xerifiedA h'y:

Sign/Date (Design Engineering)

ERSTI-04-VY 1-1409-000 Attachment 2A Page 3 of 6

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1574 MWth to 1593 MWth)

Turbine Building FW Piping (FW Pump Room)

Vibration Acceptance Criteria Peak to Peak Displacements (mils)

N-S Vertical E-W Location Meas. Accep. Meas. Accep. Meas. Accep. Sat/

Crit. Crit. Crit. Unsat Pipe Support <27.5 <25.6 <59.4 H-35 _

FCV-6-12A <31.6 <170.7 <104.7 FCV-6-12B <20.5 <11.3 <32.6 Performed by:

Sign/Date (Design Engineering)

Verified by:

Sign/Date (Design Engineering)

Acceptance Criteria Met:

Sign/Date (Design Engineering)

Note: Any UNSAT condition requires a Condition Report and an Engineering Evaluation. Request Operations to lower reactor power level to the last tested power level.

ERSTI-04-VY1-1409-000 Attachment 2A Page 4 of 6

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1574 MWth to 1593 MWth)

FIV Walkdowns Heater Bays Condensate and Feedwater Pump Rooms Plant Location Vibration Level Observation Sat/Unsat Sign/Date Comments*

Condensate Pump Room Piping /

Feedwater Pump Room Piping _ /

Heater Bay Piping Systems:

Condensate Piping /

Feedwater Piping /

Main Steam Piping /

MS Low Point Drains /

Extraction Steam /

Heater Drains /

Feedwater Heater Level Control /

Miscellaneous Remaining Systems /

ERSTI-04-VY1-1409-000 Attachment 2A Page 5 of 6

Attachment 2A Flow Induced Vibration Data Collection At 1593 MWth (1574 MWth to 1593 MWth)

Acceptance Criteria:

Piping: For main piping, if the level of vibration is too small to be perceived, and the possibility of fatigue issues is judged to be minimal, the piping system is acceptable.

Any observed vibration levels piping judged by walkdown personnel to be a potential concern will be monitored utilizing hand-held vibration meters and evaluated.

System/Components: Baseline inspections of systems and components were performed at OLTP (documented in Calculation VYC-2330). Results of EPU power ascension testing inspections/walkdowns will be compared to baseline inspection results to determine if acceptability is maintained.

Any UNSAT condition requires a Condition Report and an Engineering Evaluation.

Request Operations to lower reactor power level to the last tested power level.

Performed by:

Sin pVnDate (Design Engineering)

Verified by:

Si gn/Date (Design Engineering)

Acceptance Criteria Met Sign/Date (Design Engineering)

Record instruments used and calibration due dates:

Add additional pages as needed.

ERSTI-04-VY1 -1409-000 Attachment 2A Page 6 of 6

Attachment 5A Moisture Carryover 1633 MWth (1614 MWth to 1633 MWth)

CAUTIONS

Any of the following may be indications of vessel internals damage and potential debris generation (loose parts). (SIL 644 Revision 1)

Main Steam Line steam flow indication imbalance of 5% or more.

(B064, B065, B066, B067)

RPV water level difference >3 inches step change between level instruments from different reference legs. (B040, B041, B047 versus B021, B042, B043)

Sudden drop (<1 minute) in steam dome pressure of >2 psig. (1B048, B049)

Statistically significant step increase of moisture carryover >50% of previous value (per OP 0631, Radiochemistry, Appendix F)

Unexpected trends in parameter values that may be indicative of loss of steam dryer integrity, particularly unexplained changes in trends.

1.0 Monitor the following ERFIS points;

B021 REACTOR WATEER LEVEL 72A

B040 REACTOR WATER LEVEL 72B

B048 REACTOR PRESSURE 56B

B049 REACTOR PRESSURE 56A

B022 MAIN STEAM FLOW

B064 MAIN STEAM LINE A FLOW

B065 MAIN STEAM LINE B FLOW

B066 MAIN STEAM LINE C FLOW ERT-04-VY1 -1409-000 Attachment 5A Page 1 of 6

Attachment 5A Moisture Carryover 1633 MWth (1614 MWth to 1633 MWth)

B067 MAIN STEAM LINE D FLOW

M084 RX A UPPER REF LEG TEMP

M085 RX A LOWER REF LEG TEMP

M086 RX B UPPER REF LEG TEMP

M087 RX B LOWER REF LEG TEMP

/I Initial Date Time 1.0 Hold Criteria:

1.1 Moisture carryover exceeds 0.10%.

2.0 Request Chemistry to perform moisture carryover testing per OP 0631, Appendix F. Attach results per Step 9.0 of the main body of the procedure.

Initial Date Time

3.0 Record

reactor power: %

Recirc flow: %

Moisture carryover: %

Initial Date Time ERT-04-VY1 -1409-000 Attachment 5A Page 2 of 6

Attachment 5A Moisture Carryover 1633 MWth (161.4 MWth to 1633 MWth) 4.0 Evaluate results as follows:

4.1 IF moisture carryover is equal to less than 0.10%,

THEN no further actions are required.

il Initial Date Time I I_

Verified Date Time 4.2 IF moisture carryover is greater than 0. 10%, THEN:

4.2.1 Notify Shift Manager and Test Engineer.

l l Initial Date Time 4.2.2 Enter ON 3178, Increased Moisture Carryover

/ I_

Initial Date Time f I TI Verified Date Time 4.2.3 Take actions per the Attachment, Table 2.

Consult Technical Specifications.

t I TI Initial Date Time Verified Date Time ERT-04-VY1-1409-000 Attachment 5A Page 3 of 6

Attachment 5A Moisture Carryover 1633 MWth (1614 MWth to 1633 MWth) 4.2.4 Request Reactor Engineering to store data for individual bundle powers and flows for the approximate time Chemistry obtained the moisture carryover samples per OP 0631. Attach results per Section 9 of the main body of the procedure.

/ /

Initial Date Time

_ / /

Verified Date Time 5.0 Acceptance Criteria:

5.1 Level 1: Moisture Carryover less than or equal to 0.35%

5.2 Level 2:

5.2.1 MSL moisture content ratio as determined by Chemisbty shall be less than or equal to 0.10 %. (Reference 21A3317, Revision 0 Standard Requirements for Steam Dryer Units).

5.2.2 MSL moisture content ratio as determined by Chemistry shall be less than or equal to 0.35% WITH an approved engineering evaluation that supports continued plant operation.

ERT-04-VYl *1409-000 Attachment 5A Page 4 of 6

Attachment 5A Moisture Carryover 1633 MWth (1614 MWth to 1633 MWth) rable 1 Parameter Surveillance Frequency

1. Moisture Carryover Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Notes 1 and 2)

Notes to Table 1:

1. If a determination of moisture carryover cannot be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of achieving an 80 MWth power plateau, an orderly power reduction shall made within the subsequent 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to a power level at which moisture carryover was previously determined to be acceptable.

2. Provided that the Level 2 performance criteria in Table 2 are not exceeded, when steady state operation at a given power exceeds 168 consecutive hours, moisture carryover monitoring frequency may be reduced to once per week.

ERT-04-VY 1-1409-000 Attachment 5A Page 5 of 6

Attachment 5A Moisture Carryover 1633 MWth (1614 MWth to 1633 MWth)

Table 2 Performance Criteria Not to be Exceeded Required Actions if Performance Criteria Exceeded and Required Completion Titles Level 2: 1. Promptly suspend reactor power ascension until an engineering evaluation concludes that further power ascension is justified.

Moisture carryover exceeds 0. 1%

-OR- 2. Before resuming reactor power ascension, the steam dryer performance data shall be reviewed as part of an engineering

Moisture carryover exceeds 0.1% and increases evaluation to assess whether further power ascension can be made by > 50% over the average of the three previous without exceeding the Level 1 criteria.

measurements taken at > 1593 MWt Level 1: 1.. Promptly initiate a reactor power reduction and achieve a previously acceptable power level (i.e., reduce power to a

Moisture carryover exceeds 0.35% previous step level) within two hours, unless an engineering evaluation concludes that continued power operation or power ascension is acceptable.

2. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , re-measure moisture carryover and perform an engineering evaluation of steam dryer structural integrity. If the results of the evaluation of dryer structural integrity do not support continued plant operation, the reactor shall be placed in a hot shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the results of the engineering evaluation support continued power operation, implement step 3 below.

3. If the results of the engineering evaluation support continued power operation, reduce further power ascension step and plateau levels to nominal increases of 20 MWth and 40 MWth, respectively, for any additional power ascension.

TABLE 2 NOTES:

IF the Level I or Level 2 performance criteria are exceeded, THEN either suspend reactor power ascension (Level 2 Perfonmance Criteria) or reduce reactor power (Level 1 Perfonnance Criteria),

initiate a Condition Report, and evaluate the cause of any exceedance of the performance criteria.

Reactor power operation that results in moisture carryover that are less than the Level 2 performance criteria in Table 2 is representative of fully acceptable steam dryer perfonmance.

ERT-04 VY I-1409-000 Attachment 5A Page 6 of 6

BVY 06-019 Docket No. 50-271 VYNPS EPU Portions of Test Procedure ERSTI-04-VYI-1409-000 Power Ascension Test Procedure for Extended Power Conditions 1593 to 1912 MWth (February 24, 2006)

Attachment 9 to PATP Supplemental System Monitoring Plans for EPU Plan Total number of pages In this,Afachment (excluding this cover sheet) is85.

VYNPS EPU Power Ascension Testing 345 KV System Monitoring Plan (3 pages)

EPU Power Ascention Testing 345K System Monitoring Plan System Number: 345e System Engineer Ken Sweet Naequ ActionL~eves Level ALevtn~els Actions Required Iesnorote 163Me 1m7 MwTh 1752 MwTh 1835 MwTh 11112 MwTh addspatchnng ss RquiabletGradamayerresolAeeby loa.s eContatn Ver ote Increased Monitoring, VELCO ERFIS Pt. E037 Nonal VELCOne Limits for to notify W Operations of Monitored By SE by 340 Line (MVAR) System 2 Ambient and possible PA hold. VELCO Contacting Veco system bad.

MontorngReliable Grid may resolve by dlspatching Increased Monitoring, VELCC ERFIS Pt. E036 Normal VELCO Une Limits for to notify VY Operations of Monitored By SE by Monitoring Reliable Grid may resolve by dispatching system load.

3 Line (M) System 2 Ambient and possible PA hold. VELCO Cnatn e Increased Monitoring, VELCO (MVAR) System 2 Ambient and possible PA hold. VELCO Monitored By SE by system load.

379 Line ERFIS P'L E016Noma VELCoSyste LinUmits for to notify VY Operations of MntrdB Eb Sysitemi Relable Grid may resolve by dispatching Cnatn ec Increased _ VELCO

_itoring, 379 Line (MW)P.E02 Vec System 2 Line Limits f r to ntif VOeatios o Monitored By SE by (M) Mntrn mbetadpsil PA hod VECOCnatgVlo EPU Power Ascention Testing - 345K System Monitoring Plan Page 1 of 3

Equipment Para8 Alert and Alert and Action Acin eurd Reason or other 19 wh17 wh152M~ 85M~ 92M~

NaeAction Levels Level LeinsRqurdve3Mwh163swh172MIh13nMfo112M~

_ iD Basis L Circle A or B Increased Monitoring, VELCO e ERFIS Pt E017 Normal VELCO Une Limits for to notify VYroperationso Monitored By SE by 381 Line ERFIS Pt. E003 System 2 Ambient and possible PA hold. VELCO Monitored By SE by (M ) Monitoring Reliable Grid may resolve by dispatching Contacting Veio system load.

Increased Monitoring, VELCO ERFIS Pt. E003 Normal VELCO VLmits Une for to notify VY Operations of Moniored By SE b 381 Line (M) System 2 Ambient end possible PA hold. VELCO B Sb Contcingored Monitoring Reliable Grid may resolve by dispatching ~tcn ec system load.

VELCO Voltage Increased Monitoning, VELCO 345 KV Voftage VY'~Generator VELCO Voltage 2 Schedule (123V to notify Y Operations of MntrdB Eb (South Bus) (Relay House) Schedule light load, 125V possible PA hold. VELCO Contacting Vedol pekoa) may resolve by dispatching Vlc peak oad)system load.

- - - -F

-= - ----

EPU Power Ascention Testing - 345K System Monitoring Plan Page 2 of 3

1593 MWth Data Recorded By.

Date:

1593 MWth Data Recorded By.

Date:

1673 MWth Data Recorded By.

Date:

1673 MWth Data Reviewed By:

Date:

1752 MWth Data Recorded By.

Date:

1752 MWth Data Reviewed By:

Date:

18,95MWth Data Po,-nn.A By Date:

1853 MWth Data Recorded By Date:

1912 MWth Data Recorded By Date:

1912 MWth Data Reviewed By Date:

EPU Power Ascention Testing - 345K System Monitoring Plan Page 3 of 3

VYNPS EPU Power Ascension Testing AOG / AOGCCW System Monitoring Plan (9 pages)

IEPU Power Ascention Testing - AOG / AOGCCW System Monitoring Planl System Number: AOG: N/A AOGCCW: V70-xx System Engineer Brian Naeck Equipment Para Alert and Alr n cinReason or 153Mh173Mh152wh182wh192Mh Namd Action Lv Aler ad Actions Required 1593 Iwoh 1673 Mwh 17Q Mwnh 1832 MwTh 1912 MwTh MeoID- Basis Levels t If Circle A or B RDwor H2AN-2921A/B Both UnIts: 1. Per ARS 50-C. Notify b %

H2 Detector 1. ~-25% Engineering Moireby C%

O0102. Per ARS 50-C-6, Notify Ops ARS: 50-C-5 2. >50°% Engineeing

& 50-P-S Level 4 Recombiner H2AN-2922A.B 3.>10% 3. Declare hop & Swap -C5%

H2 Detector Disgremen9Reombner OP010 1. 5,000 cpm 1. NotifynRP & 3127Mn- 600 RAN-OG-3127 ODCM 4.3.4 Engineering Monitored by cpM Rad Monitors & T.4.1.2. 2. 10,000 cpm 2. Per ARS 50-4 3128 300 RAN-OG-3128 ARS 50-M-4 & AM Level 4 50-M-6 SM5 3. 200,000 mo0Wmm cpm L.PeeAvelM-4 l 0

3. Per ARS 50 M-6 wA1 0m

< 300 OF 1. Veryify valve line-up Monitored by Seam Tmmp to TEO0@2301A/B Op 1 400 F 2. Thermography on O o35m F StamTmpt T-G-30AB P010MS-114-IA Level 4----

EPU Power Ascentlon Testing - AOG / AOGCCW System Monitoring Plan Page 1 of 5

Equipment Pam Alert and A" and A n Name Acflon Levels ALeetanAtls f Actions Required Rteasonfor 1593 MwTh 1673 MwTh 1752 MwTh 1832 MwTh 1912 MwTh In BasisLeesohrio Circle A or B Recombiner OP 0150 < 295 OF Ver'y valve line-up, Monitored by Inlet TE-OG-2302A/B ARS 50-N2 & ps 313 OF Temperature 50-N6 > 315 OF notify Engineering Level 4 Recombiner OP 0150 < 300 OF Verify valve line-up, Monitored by Top TE-OG-2303A18 ARS 50-A-3, A- O 535 OF Temperature 4TN-3O & N-4 > 650 OF notify Engineering Level 4 OP 01 50 Mntrdb Recombiner < 450 OF Verify valve line-up, Monitored by Bottom TE-OG-2304A/B ARS 50-A-3, Ops 490 - 540 Temperature A-4, B-6. N-3, > 650 OF notify Engineering Level 4 OF

_ __ _ _ _ _ _ N-4. 0 46 Recombiner OP 0150 Monitored by Ce bnter < 300 OF Verify valve line-up, Ops ow530 -550 Center TE-OG-2305A1B ARS 50-A-3, Temperature A-4,8-6. N-3, > 650 OF notify Engineering Level 4 OF N-A, 04 MS-101-IAIB ~OP 0150 Mntrdb MS-101-A/B <75 °F Verify valve line-up, Monitored by Outlet TE-OG-2307A/B ARS 50-A-3, ps 80 - 95 OF Temperature A-4, ANN-8,

, N > 145 OF notify Engineering Level 4 3, N-A, N-5. 046 Evaporator 35 F Verify valve line-up, Monitored by Glycol Inlet TE-OG-5251A/B OP 0150 Ops 35 - 45 OF Temperature > 50 OF notify Engineering

_I__ILovalA EPU Power Ascent0on Testing - AOG / AOGCCW System Monitoring Plan Page 2 of 5

Eupet Para Nledtand Alr ndAto Levwes Actuopmntn ALeIt and ActAons Required Reason or 1593 MwTh 1673 MwTh 1752 MwTh 1832 MwTh 1912 MwTh Name Lasis other InFo ID Basis Circle A or B Evaporator < 35 OF Verify valve llne-up, Monitored by Glycol Outlet TE-OG-5252AIB OP 0150 Ops 35 45 OF Temperature > 50 F notify Engineering Level 4

-. a -a - a System Inlet Pl-1301 OP 0150 <0psig Verify valve line-up, Monitored by Pressure PI10 F05 sgOps -0.75 psig notify Engineering Level 4 Adsorber 'G' Verify valve line-up, Monitored by Outlet PP-1306 OP 0150 <-1 psig Ops -1.25 psig Pressure n Level 4 Leel 2bm Outlet P01Verify valve line-up, Monitored by StmOuet PI1-307 OP 0150 -i to I psig s0 H pslg Prsuenotify PressureLe-v-l-4 Engineering Lel EPU Power Ascentlon Testing - AOG / AOGCCW Systern Monitoring Plan Page 3 of 5

Equipmenrt Name Pam lertand BActsinse IAlertLevels and Action Actions Required Reason or other Inf 19 1o 93 M wh17 d~

1 M 1 72M~ 02M~

1392 92M~

1. notify engineering, verilf

1. 25 scfm valve line-up OP 2150 Z Initate corrective actions Del Pi / OP 0150 to prevent exceeding 100 Monitored by Deay Ppe I FIP2002 3.1.2abl Z 30ssr scfm SI Ops I 8 sarn

3. reduce power to Level 4 maintain l0 scfm

3. <100 scfm 4. Agree wIthin 10 sclm of FI-2004

1. 25 scfm 1. notify engineering, veriy valve line-up OP 2150 2. 30 scfm Monit Delay Pipe I OP 0150 2. initate correctiv actio ored by stem Flow FI-2004 ODCM Table 3. <1 00 scfm to prevent exceeding 100 8 scfm sctmLevel 4

4. Agree within 10 sWm of 3. reduce power to Fl-2002 maintain -100 scfm OP 0150 50 eF F, & Adjust temperature per OP Monitored by AOGCCW Ti14713 021 (15¶OFabove 2150 &

Temperature T-104-7153 OP2150 anbent when > RP 2188 OPS 50 -90 OF RP 2188 OF airtemp) NOify Engineering Level 4 EPU Power Ascention Testing - AOG / AOGCCW System Monitoring Plan Page 4 of 5

1673 MWth Data Recorded By:

Date:

1673 MWth Data Reviewed By.

Date:

1752 MWth Data Recorded By:

Date:

1752 MWth Data Reviewed By:

Date:

1832 MWth Data Recorded By:

Date:

1832 MWth Data Reviewed By:

Date:

1912 MWth Data Recorded By:

Date:

1912 MV D ~at R-Aw-6 wth u Wy. Date:

EPU Power Ascention Testing - AOG / AOGCCW System Monitoring Plan Page 5 of 5

[Svstem Monitoring Plan System Name: Date Issued:

AOG / AOGCCW I I I I I 101212004 Rev. I System Number: AOG: N/A AOGCCW: V70-xx System Engineer: Brian Naeck Equipment No./ ID Parameter Source M /T Freq Act and Required info System Per M-Rule Per M-Rule Reliability N/A MRFFs N/A N/A M N/A Program Pmrogrm Scopping Basis

_ NPTOMonitored by SJAE Flow N/A * ~~IL ui U PiO uu~ PIOOps Recombiner OP 0150 TS 0Mie H2 Detector H2AN-2921A/B % LEL H2 H2AN-2921A/B Logs M OP 0150 ARS: 50-C-5 ARS: 35.8C Mon

& 50-P50 & -6 OP 0150 Recombiner OP 0150 OP 0150 TS 3.8.J Monitored by H2 Detector H2AN-2922A/B % LEL H2 H2AN-2921A/B Logs M TS 3;8.J TS 3.8.J ARS: 50-C-6 Ops

._ _ _ &50-P-6 Rad Monitors CPS in RAN-OG-3127 PODCM5 Mo0P05d by RAN-OG-3127 Discharge RAN-OG-3128 Logs M l AODCM ODCM 4.3.4 ODCM 4.3.4 onitore y MI-G1,-3I 28O Stream & T.4-1 8 T.4.1.2.

I j& &T4 I2

Flow to Recombiner Fl-2001A/B Flow Rate to FI-2001A/ B Logs M OP 0150 OP 01 50 OP 0150 Monitored Recombiner Ops by Off Gas Inlet TE-OG- B Logs M OP 0150 OP 0150 OP 010 ME-bGy23 My Temp 234DA/B Temperate TE-OG-2340A/B Logs M OP 0150 P 0150 O 0150 OPs SeaTemper ture DE Temperature TE-OG-2301A/B Logs M OP 0150 OP 0150 OP 0150 Monitored by Recombiner aTe 2303A/B l~ Temperature ~

TE-OG-2302A/B _ Logs M

- OP a0150 OP 0150 OP 0150 Monitored by Temperature T232G- M Recombiner Top 2304AB Temperature TE-OG-2303A1B Logs M OP 0150 OP 0150 OP0150 Mops Temperature 2303AB Ops Recombiner TE-OG- Temperature E 0 Logs M OP 0150 OP 0150 OP 0150 Monitored by Bottom Temperature 2304B Tem perature _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -- a_ _ _ _ _ _

Recombiner TE-OG- Monitored by Center 2305A1B Temperature TE-OG-2305A/B Logs M OP 0150 OP 0150 OP 0150 Ops Temperature

MS-101-IAIB TE-OG- Monitored by Outlet 2307AB Temperature TE-OG-2307A/B Logs M OP 0150 OP 0150 OP 0150 Ops Temperature Evaporator Glycol TE-OG- Monitored by Inlet 5251A/B Temperature TE-OG-5251A/B Logs M OP 0150 OP 0150 OP 0150 Ops Temperature Evaporator Glycol Outlet TE-OG-5252A/B mperature TE-OG-5252A/B

-i-Monitored Logs M OP 0150 OP 0150 OP 0150 Opd by Temperature e l Pressure Pl-1301 Pressure Pl-1301 Logs M OP 0150 OP 0150 OP 0150 Monioprsed by Outlet Pressure Pl-1306 Pressure P-1:306 Logs M OP 0150 OP 0150 OP 0150 on System Outlet Pl-1307 Pressure Pl-1307 Logs M OP 0150 OP 0150 OP 0150 Monitored by Pressure Ops Delay Pipe / Fl-2002 Flow Rate FR-Ilnf Les KA OP 01 50 OP 0150 OP 0150 Monitored by Syf.temn-F jO-D-CIM~ ODCM ODCM Ops

Delay Pipe I FP12004 Flow Rate F1-2002 Logs M OP 0150 OP 0150 op 0150 Monitored by System Flow ODCM ODCM ODCM Ops pH Iron EPRI Guidelines Copper Surv. are changing, AOGCCW System ~ ~ hloridemoetflow Chemistry N /A Corrosion NIA (grab T Q OP 4623 OP 4623 mre toafollow Cestyinhibitors sampleMoirngb Specific Gravity analysis) Chemistry (i.e. GlycolChmsr Concentration)

Surv.

AOG 'Giycoi' Conductivity Monitoring by Chilled Water N/A Chlorides N/A (grab T Q OP 4623 OP 4623 Monitry System Filterable Solids sample hemistry Chemistry analysis)

C hiller Pump A/B P AGG- Pressure PI-OGG- Logs M OP 0150 OP 0150 OP 0150 Moni d by Pressure

'O . . .. ... - . . .. . .. . . . ... .. . . . . .. ..

VYNPS EPU Power Ascension Testing Condensate Demineralizer System Monitoring Plan (2 pages)

EPU Performance Monitoring for Condersate Demineralizer System Increased Power Level Evaluation Points Eq~fetN.Alarm I ~h17 1593 ~h15(91.55%) MWth 1832 Myyth 9192MWlh Ato o Pareter Values/Llmts 27psid Aa 2 f Level (83(32%)

251 t (87.848%)

20 -

(95%81%) (100%)

- 8 17 15_

Actio 2valuate margin to 55psid Dimitfor DM-1-1A Data

-3250gpm system dP: Fluff resin; Backwash 92 Fow 3250g 2 -2600gpm -2760gpm -2 5gpm -3095gpm Data __17____'Investlyate why flows are not balarced dP 25Drad 2 25 20 18 17vauate margin to lit for _5psid Data _ system dP; Fluff resin; Backwash Flow 3250gpm 1 2 -2600gpm -2760gpm -2925gpm -3095gpm -3250gpm Data Investigate why flows are not ballarced dP .2 25sid 25 20 18 17 15 Evaluale margin to 55psid limit for DM-1-1C Data system dP, Fluff resin; Backwash Flow 3250gpm 2 -2600gpm -2760gpm -292&gpm -3095gpm -3250gpm Data Investigate why flows are not ballar ced d' 251.d 2 25 20 18 17 15 Evaluate margin to 55psid limit for DM-1D Data . system dP: Fluff resin; Backwash Flow 3250gpmn 2 -2SO0gpm -2760opm -2925gpm -3095gpm -3250gpm Data Investigate why flows are not balarced dP 25psId 2 25 20 18 17 15 Evaluate margin to 55psid Omitfor DM-t1-E Data 292 system dP; Fluff resins Backwash

_Flbw 3250gpm 1 2 -2600gpm -2780gpm - 5gpm i3095gPm -3250gpm Data _ = = Invesbgate why flows are rnotbatianced System dP S5pskd r5psid 2 55psld 55psid 55psid 55psid Evaluate prior dab br which vessel pu Data systemn hito Flow Balance Override S-14-IA dP 20psId 2 15 16 17 19 20 Data . Backwash Ftiter Evaluate repltacefent S-14-1B dP 20pskd 2 15 16 17 19 20 Data = ; Backwash Flter; Evaluate replacerr ent I_

S-14-iC dP 20pskd 2 15 16 17 19 20 JI Data Backwash Ftiter; Evailuate replacerr et S-14-1D dP T 20psId 2 15 16 17 19 20 Data Backwash Fiiter Evaluate repiacerrent S-14-IE dP 20psId 2 15 16 17 19 20 Data_ Backwash Flter Evaluate repacement ConducLhrity Monitored Iw Chemistrv Comrnrsnts:

General Guidance 1593 Mwth Reviewed By. Data can be colected at the Condemln Pdntl/SnIOlt. control panel on the 232 level of the Approved By: Turbine bulding. System dP and vessw PrMUSgniate flows are available on the recorder located at the panel. Vessel dcPis 1673 Mwth Reviewed By. visible along the upper nght corner of Prninvuan.t. the panel.

Approved By.

PdnUYignaDn 'Data can be obtained shiffly via OP 0150.05 data sheets 1752 Mwth Reviewed By.

PdnVSlgarDate 'Chemisiry Is performing additional daly Approved By: . .

trending of Condemin performance ior PdnVS~igrnDal. the schedtuing of vessel backwashes 1832 Mwth Reviewed By: 'it is the Intent of this monitoring plan PrdntUSignlDat that any parameter approaching an Approved By: evaluation limIt be monitored on a more Prnt/Sigeabt. frequent basts to preclude the system from entering flow ballance override at 1912 Mwth Revbewed By: 55psid system dP before action Is taken PrfnhSianDale to reduce overall system dP.

Approved By PdntfSfn/ate 02125/2006

SUMMARY

OF CONDEMIN FILTERED BYPASS FLOW CASES CASE DESCRIPTION MODELED TRAP dP TRAP Dp DEMIN Dp HEADER TOTAL FLOW MASS FLOW OUTLET E AVE DEMIN BYPASS BYPASS

(@ current flow) ACTUAL PSID Dp GPM E6 #IHR VALVE %OPEN FLOW GPM FLOW % OPEN 1 CURRENT POWER 7 8.7 5 27.5 13000 6.435 90 2600 0 2 CURRENT POWER 7 8.7 20 41 13000 6.435 70 2600 0 3 CURRENT POWER 12 13.4 5 32.5 13000 6.435 90 2600 0 4 CURRENT POWER 12 13.7 20 46.5 13000 6.435 70 2600 0 5 105% 5 demins online 7 9.8 5 29.5 13810 6.836 70 2760 0 6 105% 5 demins online 7 10 17 40.7 13810 6.836 90 2760 0 7 105% 5 demins online 12 15.6 5 37 13810 6.836 70 2760 0 8 105% 5 demins online 12 15.5 17 46.5 13810 6.836 90 2760 0 9 105% 4 demins online 12 NR 17 NR 13810 6.836 NR NR NR 10 110% 5 demins online 7 9.8 5 29.7 14625 7.239 70 2925 0 11 110% 5 demins online 7 10.1 17 41.7 14625 7.239 70 2925 0 12 110% 5 demins online 12 17.2 5 39 14625 7.239 70 2925 0 13 110%5 demins online 12 17.1 17 51.7 14625 7.239 90 2925 0 14 11% 4 demins online 1 12 .5 17 4. 14625 7.239 70 27553 3 15 115% 5 demins online 7 10.5 5 32.3 15465 7.655 70 3095 0 16 115% 5 demins online 7 8.5 1 4734 15465 7.655 70 3095 0 17 115% 5 demins online 12 18.7 5 42.1 15465 7.655 70 3095 0 18 115% 5dernins online 12 18.7 17 54 15465 7.655 90 3095 0 19 115% 4 demins online 12 16.7 17 51.2 15465 7.655 90 2930 3845 50 19A 115% 5 demins online 7 11.5 5 35 15465 7.655 70 3095 0 19B 115%4deminsonline 7 13 5 38.5 15465 7.655 70 3075 3170 50 20 120% 5 demins online 7 11.5 5 35.8 16250 8.044 70 3250 0 21 120% 5 demins online 7 12 17 46.2 16250 8.044 90 3250 0 22 120% 5 demins online 12 19.8 5 45.8 16250 8.044 70 3250 0 23 120% S demins online 12 20.5 17 57.5 16250 8.044 90 3250 0 23A 120% 5 demins online 10 17 15 51.5 16250 8.044 3250 3250 90 238 120% 5 demins online 1 17 17 53 16250 8.044 3250 3250 90 23C 120% 5 dernins online 10 17 20 57.5 16250 8.044 3250 3250 90 123D 123D 1120% 5 demins 11200 demnins-- online online

- .1. 121

.J. 20

-- 151

--. 9 54.51

5 162501

. 8.044

--- 3250 32501 901

VYNPS EPU Power Ascension Testing Nuclear Boiler Vessel Instrumentation System Monitoring Plan

(.2 pages)

VY EPU NBVI Supplemental System PerFormance Monitoring AstParameter A" ArtIn Ae Parameter ID Action Source ; l Calculated Reference Leg A Temp 'F C220 OP4390 4 Evaluate Calculated Reference Leg B Temp 'F C221 OP4390 4 Evaluate RX A Upper Reference Leg Temp 'F MOB4 OP4390 4 Evaluate RX A LoUer Reference Leg Temp 'F MO5S OP4390 4 Evaluate RX A Upper Reference Leg Temp 'F MOSS OP4390 4 Evaluate RX B Lower Reference Leg Temp 'F MOBS OP4390 4 Evaluate R Vessel Stud Temp F 8023 4 Evaluate Vessel Head Fbnge Temp 'F 8024 4 Evaluate Vessel Heed Adjacent to Flange Temp 'F S025 4 Evaluate Vessel Bottom Drain Temp Temp 'F S026 4 Evaluate Vessel Skirt at MTG Flange Temp 'F S027 4 EVaAU Vessel Bottom Head Temp IF S028 4 Evaluate Vessel Skirt Near Joint Temp 'F S029 4 Evaluate Vessel Above Skirt Joint Temp 'F S030 4 Evaluate Vessel Downcomer Temp 'F S031 4 Evaluate Vessel Core Temp 'F 8032 4 Evaluate Nozzle N4C In Board Temp IF S033 4 Evaluate Vessel Below Water Level Temp 'F S034 4 Evaluate Total Jet Pump Flow Loop A M#/HR B051 4 Evaluate Total Jet Pump Flow Loop B M#/HR 8052 4 Evaluate Total RX Jet Pump Flow M#IHR B012 5105 M t/HR? 4 Evaluate Flow to Ref Leg FIT-400-A GPM NIA 0.0014.005 GPM OP0150 4 Evaluate Flowto RefLeg FIT-400-B GPM NIA 0.0014605 eaPU npn4qn A E.'

Prepared by Stan Kol 02/2512006 Page I

VY EPU NBVI Supplemental System Performance Monitoring Asset AetParameter Parameter AWlert ID AotlaioCI lction ID(ERFIS) Levels -j Req C

____ ____ _ __ ____ ___D ate to L TGA_ _ X _4v rime-GPM _ _ _ t Flaw to Ref Leg FIT-400-C GPM NIA 0.0014.0005 GPM OPOlSO 4 Evaluate Flaw to Ref Leg FIT-40O-D GPM NIA 0.0014,005 GPM OP0iSO 4 Evaluate*

1593 MWth Data Recorded By:

Date:

1593 MWth Data Reviewed By:

Date:

1673 MWlt Data Recorded By:

Date:

1673 MWth Data Reviewed By:

Date:

1752 MWth Data Recorded By.

Date:

1752 MWth Data Reviewed By:

Date:

1835 MWth Data Recorded By:

Date:

1835MWth Data Reviewed By:

Date:

1912 MWth Data Recorded By.

Dab:

1912 MWth Data Reviewed By:

Date:

Prepared by Stan Kol 02/25/2OO6 Page 2

VYNPS EPU Power Ascension Testing Core Spray System Monitoring Plan (1 page)

EPU Supplemental Performance Monitoring Plan for the Core Spray System System Engineer: Stephen Jonasch Previously Equip Parameter Pre 5% 10% 15% 20% Source Remarks Monitored ID EPU 1673 1752 1832 1912 Range MWth MWth Mwth Mwth Yes DPIS CS A -3.2 OP Note 1 Sparger 0150 Note 2 43A DP pg.1 Note 3 Yes DPIS CS B -2.9 OP Note 1

- 14- Sparger 0150 Note 2 43B DP _ pg. 10 Note 1: A minus reading is normal. Gauge range is -5.0 to +5.0. Alarm setpoint is +0.6.

Note 2: GE SIL 300, Supplement 001 was provided to VY with GE's discussion on what will be the response of this gauge during power uprate. GE has stated that there should essentially be NO CHANGE in readings. Data collected during various down powers and post refuel indicate that this is probably correct.

Note 3: CR 2005-4023 reported that the 43A DP gauge was fluctuating. While not certain, there may be a small weep In the'restricting orifice flange located in the drywell that is giving these fluctuating readings. Because it is located in the drywell, this cannot be confirmed.

On/About Jan 4, the fluctuating stopped and was reading -4.5. Since that time, the reading has again changed and, as of 2/13/06, is reading -3.2. CR 2006-0460 was generated reporting this issue.

1673 Mwth Data Recorded BY: Date:

1673 Mwth Data Reviewed BY: Date:

1752 Mwth Data Recorded BY: Date: _

1752 Mwth Data Reviewed BY: Date:

1832 Mwth Data Recorded BY: Date:

1832 Mwth Data Reviewed BY: Date:

1912 Mwth Data Recorded BY: Date:

1912 Mwth Data Reviewed BY: Date:

VYNPS EPU Power Ascension Testing 22 KV System Monitoring Plan (2 pages)

VY EPU System Performance Monitoning Asset Parameter Parameter Aleveh Adt5ons IDDARiloi ID(ERFIS) Lovedll;~

_ _ = ~Dae ________

Time Expected: 17.95 KA Phase A Bus Amps (G006) Design / Operatng LUt Evaluate

___ ___ ___19 KA,

_Expected. 17.95 KA Phase B Bus Amps (G007) Design I Operating Limit Evaluate I9KA _ _ _ _ _ _ _

Expected: 17.96 KA Phase C Bus Amps (GOW) Design I Operating Limit Evaluate

_9KA __ __ _

PhaseReturn Air Temp Local hidokatbon Alarm _ Evalue Phs u F Tl-22KV-IA ~ 2 1e0F Eaut Phase B Bus Supply Air Temp 112KCV-lB A Qo 120F Eve fl-22KV40.ID110 PhsD sIF Alr emp Kv-l1C s br QorV X Evdluate= = -= = = _ =

Phase C Bus RCtur Air Tamp Local Indication Alarm 0 170F P Evaluae_

F Tl-22KV.c @ e0F Eaut Isophase Bus Cooler A (TBCCW) Outd Temp F Local Indication Ab t 1 > IIVF Evaluab Tl.104-31A AI >1DFEail Isophase Bus Cooler B (TBCCW) Outlet Temp IFLoaIniton At >1DFElue bsophase Bus Cooler A (TBCCW) Flow (GPM) Local Indication Fl Alert 'c 90 GPM Evaluate 104-2A Isophase Bus Cooler B (TBCCW) Flow (GPM) Local 104-2B Indication F Alet @ '900PM Evaluate Aet0- oGMEaut Isophase Bus Fan (GLF-1 A) or (GLF- Air Flow (CFM) Ind2atIon 11B) Ai lw(F)22KV-3A or Fl- Aler C I 1800 CFMI Evaluate 22KV-3m Thermography performed by Component Engineeuing 1593 MWth Data Recorded by: Date:

1593 MWth Data Reviewed by:__________ Date:_ ____

I I - I ----------

1673 MWth Data Recorded by: Date:

11673 MWth Data Reviewed by: Date:

1752 MWthDataRecorded by: Date:

1752 MWth Data Reviewed by: Date: ___

Nick Lisai 22KV System Engineer Page 1 of 2 a .. - -S.

VY EPU System Performance Monitoring AetParameter Pa i.I IU Asset IDParameter (EFE ID AN" Aco Actioni Reure g la 2X lg I I~

LI (ERFIS) LevelS _

-0Rqied3~~ _ _ _

- - - I Expected: 17.95 KA Phase A Bus Amps (G006) Design / Operting Unm. Evaluate 19 KA _ ___

Expected: 17.96 KA Phase C Bus Amps (0007) Design I Operating Lmit Evaluate 19KA Expected: 117.98 KA Phase C Bus Amps (Gi) Design I Operating Limit_ Evaluate 19 KA Phase A SW Return Air Temp Local Indication Abanm C 176¶F Alert Eaut F Tl-22KV-IA a :I 160VF Ea Phase BBus Supply Air Temp Local iication Alarm @176- A Evaluate T1-22KV-ID 120 F Phase C Bus Return Air Temp Local IndicatIon Alum 0 176F AeEvauate IF lr2KV.IC @~16O1F Isophase Bus Coaler A (TBCCWN) Outlet Tomp Local iation iAI Ald Isophase Bus Coaler B (TBCCW) Outlet Temp IF Local Indication Ab :,110F Evalute 71.1044318 Isophase Bus Cooler A (TBCCW) Flow (GPM) Inica Loal 104ZA Alert@l PM Evatuate l Aet~- 0GMEaut Isophase Bus Cooler B (TBCCW) Flow (GPM) Local IndIcation l Alert 0 c 0 GPMI Evaluate Isophase Bus Fan (GLF-IA) or (GLF- Local Indication FA 1B) Air Flow (CFM) 22KV-3A or P1- NAlerC I 16000CFM Evaluate 22KV-39 Thermography performed by Component Engineering ________

1832 MWth Data Recorded by: Date:

1832 MWth Data Reviewed by: Date: I I _ _ _

1A12 MWth nnata PRenrnded _ _ Dat 1912 MWth Data Reviewed bv: Date: I I_ I I I_._IIII 1 1 - _ 111 Nick Lisa!

22KV System Engineer Page 2 of 2

VYNPS EPU PDwer Ascension Testing AE I RWCU System Monitoring Plan (12 pages)

WY EPU System Performance Monitoring ParameterstemWPerformanceFMonitoring Asset Ase Parameter armee Alettn AcSion Acii nOo 2 ID (RIS) Lo ~Required . 0)tz M P N N Date_

Time SJAE SJAE Off (BOPM002) nta nla Gas Radiation (0P 02n/na SJAE RM-17.151 Alert - > 1E-6 > 2E restore SJAE Off Gas CRP 9-10 Action - > 2E-5 2 to < t E-6; CR Lin Rad (Cl/sec) OP 0150.03 [pg. 16] ODCM = 1.6E-1ClIsec [TS 4.8.K1 = ODCM]

SJAE SJAESteam (T032) n/a _

Flow (Ibm/hr) OP 0150.03 [pg.251 n/a SJAE SJAE Press P 101-23 Alert<111, >119 <1, PCV->120

_________________ _ Press__ O 015.0 9pg-6 Action cl110,>120 psig adjust PCV-1 OF 4 _1_50.3-[pg.

CR 12-132 (RWCU) DI Inlet Conductivity CRP 9-4 AlertActon - > 0.3 Notify Chemistry OP 0150.03 [pg. 81 _

CR 12-135 (RWCU) DI Outlet Conductivity A CRP 9-4 1 -> 0.1 3 Notify Chemistry OP 0150.03 (pg.8) _. _

CR 12-135 Conductivity B CRP 9-4 Alr -' 0.1 Notify Chemistry Op 01t50 .0 3" - R TI12.137 C (RWCU) Pt 1 Temperature CRP 9.4 perTS Fig. 3.6.1 1 [TS 3.6A.1]

OP 0150.03 (pg. 8) _ _ _ _ _ _ _ ____

Tl 12.137 Isolate Demineralker (RWCU) Pt 3 CRP 9-4 AetActon - > 140 F I D nWR/CRae OP 0150.03 (pg. 8)

(RWCU) P-49-IA Amps CRP12-4M>l2 AmsA WR, CR OP 0150.03 (pg. 8) Ps* ___

(RWCU) P-49-1 B Amps O 0p l > 5 Amps OP 0150.03 (pg. 8) >2Ap (RWCU) Avg of Demin Flows GPM (3DMA009) n/a I_ n/a _ *____

RWCU Flow M# / HR (C009) > 0.060 mlthr l CR_ l__i RWCU System Inlet Temp F (B023) l > 550 FA_

RWCU System Outlet Temp F (B024) CRF (RWCU) Demin Flow A M# / HR (B017) n/a nta

_ _ _ _ _ __ ii (RWCU) Demin Flow B M# / HR (9018) l n/a n/a *

(RWCU) ROC F / HR (COs9) l n/a n/a *

(RWCU) Flow GPM j 054) n/ia nra

Parameter Parameter Ac_ D ID Action Aco~SCo LO (ERFIS) -. LevelsReurd S Jeff Melvin System Engineering Page 1 of 4

WYEPU System Performance Monitoring

.l Date

_ __DTime

_____

RHX Outlet Temp F (8055) n/a n/a to NRHX__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

NRHX Outlet Temp F (B056) n/a l n/a__

ds (RWCU) Thermal Power _(OP014)% n/a (RWCU) A Flow F FT75Aa n/a Local [2801 (RWCU) B Flow F FT-7LB n/a n/a (RWCU) Demin A DIP F dPIS94A n/a n/a Local (2801 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(RWCU) Demin B D/P F dPalS-8 n/a n/a (RWCU) Resin Trap A DIP F LdPIS72A n/a n/a (RWCU) Resin Trap B D/P F dPIS-728 n/a n=a Local (2801 _ _ _ _ _ _ _ _ _

Reactor Pressure P1-2-34608 n/a n/a

__ _ __ _ _ _ _ _ PSIG S of Rk25-6 / /

RWCU Pump Suct PP-12-114 n/a n/a PSIG Rk 25-2__ _ _ _ __ _ _

(RWCU) 'A' Pump Brg Clr Out Rk 25-2 n/a n/a (RWCU) 'B' Pump Brg_ Clr Out TIS-12-89B n/a n/a

_ __ _ __ _ _ _ F Rk 25-2 W ~

RWCU Pump Disch P142-87 n/a n/a PSIG Rk 25-2 _ _ _ _ _ _ _ _ _ __ _ _

Regen HX Out PPR12-5 n/a n/a PSIG Rk 25-2 _

Non-Regen HX Out P1-12-95 n/a n/a PSIG Rk 25-2 _ _ _ _ _ _ _ _ _ _ _

Non-Regen HX Out TIS-12-99 n/a n/a F Rk 25-2 NRHX (RBCCW) Out TC4k04-5 n/a n/a

_____ ______ ___ __F Rk 25-2 _ _ _ _ _ _ _ _ _

RWCU Demin Inlet TIS-12-115 n/a n/a F Rk 25-2_

(RWCU) Demin Effluent P1412-113 n/a n/a

__ __ __ _ PSIG Rk 25-2 _ _ _ _ _ _ _ _

Jeff Melvin System Engineering Page 2 of 4 V

VY EPU System Performance Monitoring

_ - , , _ , I_ I Parameter Alertt Asset Parameter ID Action .3 Actions I F g iF N 0

0, ID Required 9 in (ERFIS) Levels co 0° 4 4 - - Y 1 _ -

Data-SJAESJAE ~~~Gas SJAE Off Radiation (SOPM002)

(OMO)rl r We

/

SJAE RM-17.151 Alert- < IE-6 2E-5 -stor SJAE Off Gas CRP9-10 Action - < 2E-5 2 to > 3E-2; CR Lin Rad (Ci/sec) OP 0150.03 [pg. 16] ODCM = 1.6E-1CI/sec [TS 4.8.K.1 = ODCM] _ _ _

SJAE SJAESteam Flow (Ibm/hr) (T032)[pg.25]

OP 0150.03 n/a n/a Pi 101-23 Alert<1 I .>1 19 <c110,>120 SJAE SJAE Press CRP *-6

_____________OP 0150.03 [pg 4 Actionl <1 10, >120 psig adjust PCV-1 (RWCU) Dl Inlet Conductivity CRP 124 A9Son - > 0.3 _ oTSr4.6.B.3.bC

___________ OP 0150.03 [pg. 8j T .6B3b CR 12-135 _ ____ _ _

(RWCU) Dl Outlet Conductivity A CRP 9-4 1- '0.1 Notify Chemistry

.P 0~150.03 (pg. )

CR i2-135 Conductivity B CRP 9-4 A - > 0.1 Notify Chemistry OP 0150.03 (pg. 8) _ _ _ _

UP12-137 (RWCU) Pt 1 Temperature CRP 9-4 per TS Fig. 3.6.1 1 CR Ti 12-137 Isolate Demineralizer (RWCU) Pt 3 CRP 94 AlertAction->140F WR/CR OP 0150.03 (pg. 8) _ _ _

12-A-MIIM2 (RWCU) P-49-IA Amps CRP 9-4 AeAconWR, CR OP 0150.03 (pg. 8) > 52 Amp 12-A-MIM2 AeU o (RWCU) P-49-1 B Amps CRP 94 > 52 Amps WR CR OP 0150.03 (pg. 8)

O 5 Amps (RWCU) Avg of Demin Flows GPM (30MA009) Wea n/a_ _ _

RWCU Flow M#/ HR (C009) >A0.060 mCR/hr CR RWCU System Inlet Temp F (8023) >A550 F _CR RWCU System Outlet Temp F (8024) Ae450 F CR (RWCU) Demin Flow A M# / HR (B017) n/a ata (RWCU) Demin Flow B M# / HR _ -.,____a_ rva (RWCU) ROC F/HR (C039) n/a r nta _

Jeff Melvin System Engineering Page 3 of 4

WY EPU System Performance Monitoring

_ _P = lr Ste Perac Mon itoring Parameter Alertt Asset Parameter ID Action Actions I F uiz I ZR ID j Required 8 (ERFIS) Levels CoU C i, co~

N 8 C4

Z. N Da__t_

Time -

(RWCU) Flow GPM (3054) n/a nf/a _ _

RHX Outlet Temp F (9055) n/a n/a NRHX Outlet Temp F (8056) nla nea (RWCU) Thermal Power (800P014) n/a n/a _

(RWCU) A Flow Local [2801 n/a nta (RWCU) B Flow F FT.75B n/a n/a

_________________________ ~~Local 12801 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _

(RWCU) Demin A D/P F dPIS94A n/a nfa Local 12801n/

(RWCU) Demin B D/P F LPcSl920 n/a n/a _

(RWCU) Resin Trap A D/P F dPIS-72A n/a n/a

__ __ _ _ __ __ __ __ _ __ _ __ _ _ __ __ _ _ Local 12801 _ _ _ _ _ __ _ __ _ _ _ _ _

(RWCU) Resin Trap B D/P F dPIS-72B n/a n/a

_________ ________ _____ ___ ________ Local [2801 _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ __ _ _

Reactor Pressure PSIG Pl-2d"08 P12of- 2a _~ /

R_ CUPu_-_

_ sui_ PSIG o Rk 25-2 n/a n/a uv iJYnS , 12-NA1 n/a r/a (RWCU) A Pump Brg CIr Out F Rk 25-2 n/a r/a (RWCU) 'B Pump Brg CIr Out TIS-12-89B nta Ina F Rk 25-28ntna RWCU Pump Disch PPSIG n/ n/a PSIG Rk 25-2 nta nta _ _

Regen tX Out PP-12-95 n/a n/a PSIG Rk 25-2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Non-Regen HX Out P1-12-46 NO/W PSIG Rk 25-2 _ _ _ _ _ _ _ _ _

Non-Regen HX Out _ F naS-1299 n/a

__Rk 25-2 _ _ _

NRHX (RBCCW) Out TC-102 n/a n/a F Rk 25-2 __

RWCU Demin Inlet TIS412-115 nOa n/a Dem FRWCU Rk 25-2 nta r a _

(RWCU) Demnin Effluent P1-12-113 Wea n/a

____ ____ ___ PSIG Rk 25-2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1S98 MAfDatah / _______________ Reviewed RaOCrdad bV'y: ____________________________________________ by: /I 167a MWth Data Recorded by: ____________________________________I Reviewed by: ./

1752 MWth Data Recorded I _____________ Reviewed by: ________________________________________ by: I 1832 MWth Data Recorded by: ____________________________________I Reviewed by: /

1912 MWth Data Recorded by: ____________________________________I ____________ Reviwe by Jeff Melvin System Engineering Page 4 of 4

R*TIME (DO NOT EDIT!) . ."*M _ t&A d .a .*= sm" .dtGU cOOPQW4 Point ID BOPMo02 T032 3DMA009 C009 B023 B024 B017 B018 C039 B054 B055 BOP014 RWCU SJAE INLET OFF RWCU RWCU RWCU RWCU TEMP RWCU RWCU RWCU GAS SJAE RWCU SYSTEM SYSTEM DEMIN DEMIN RATE RECIRC REGEN LOOP ACT STEAM SYSTEM RWCU INLET OUTLET FLOW FLOW OF PUMP HX THERMAL Point Description IAV FLOW FLOW FLOW TEMP TEMP A B CHANGE FLOW OUTLET POWER Engineering Units LB/HR GPM MLB/HR DEG F DEG F M#/HR M#/HR F/HR GPM DEG F 2/01106 11:21:00 4.81 10657.03 64.74 0.06 510.82 445.27 0.03 0.03 0.01 154.49 184.35 1.43 2/01/06 11:22:00 4.89 10667.19 64.80 0.06 510.74 445.27 0.03 0.03 -0.19 154.49 184.16 1.43 2/01106 11:23:00 4.85 10659.38 64.92 0.07 510.63 445.15 0.03 0.03 -0.12 154.49 184.21 1.44 2/01/06 11:24:00 4.87 10647.65 64.96 0.06 510.71 445.23 0.03 0.03 -0.99 154.49 184.45 1.43 2/01/06 11:25:00 4.85 10661.72 64.83 0.06 510.98 445.19 0.03 0.03 -0.94 154.49 184.12 1.43 2/01/06 11:26:00 4.94 10688.28 64.99 0.07 510.90 445.27 0.03 0.03 -0.77 154.49 184.64 1.44 2/01/06 11:27:00 4.88 10648.44 64.76 0.06 510.78 445.23 0.03 0.03 -0.38 154.49 184.16 1.43 2/01/06 11:28:00 4.89 10633.59 64.83 0.07 510.90 445.19 0.03 0.03 -0.18 154.49 184.16 1.44 2/01/06 11:29:00 4.85 10644.53 64.79 0.06 510.82 445.19 0.03 0.03 0.40 154.49 184.16 1.43 2/01/06 11:30:00 4.84 10619.53 64.89 0.06 510.86 445.23 0.03 0.03 0.73 154.49 184.21 1.43 2/01/06 11:31:00 4.85 10654.68 64.94 0.07 510.94 445.47 0.03 0.03 0.62 154.49 184.45 1.44 2/01/06 11:32:00 4.93 10631.25 64.78 0.06 510.75 445.27 0.03 0.03 0.68 154.49 184.26 1.43 2/01/06 11:33:00 4.88 10674.21 65.02 0.06 510.78 445.31 0.03 0.03 0.44 154.49 184.16 1.43 2/01/06 11:34:00 4.80 10640.62 65.03 0.07 510.86 445.23 0.03 0.03 0.00 154.49 184.49 1.43 2/01/06 11:35:00 4.95 10658.59 64.94 0.06 510.63 444.99 0.03 0.03 -0.58 154.49 184.16 1.43 2/01/06 11:36:00 4.87 10647.65 64.77 0.07 510.82 445.11 0.03 0.03 -0.58 154.49 184.26 1.44 2/01/06 11:37:00 4.83 10664.06 64.95 0.06 510.90 445.11 0.03 0.03 -0.65 154.49 184.16 1.43 2/01/06 11:38:00 4.82 10677.34 64.91 0.06 510.78 445.15 0.03 0.03 -0.53 154.49 184.07 1.43 2/01/06 11:39:00 4.87 10628.90 64.70 0.06 510.86 445.15 0.03 0.03 -0.25 154.49 184.21 1.43 2/01/06 11:40:00 4.87 10685.15 64.88 0.06 510.94 445.23 0.03 0.03 -0.08 154.49 184.17 1.43 2/01/06 11:41:00 4.85 10629.69 64.84 0.07 510.82 445.19 0.03 0.03 0.16 154.49 184.26 1.44 2/01/06 11:42:00 4.87 10678.91 64.74 0.06 510.86 445.23 0.03 0.03 0.51 154.49 184.21 1.43 2/01/06 11:43:00 4.80 10653.91 64.83 0.06 510.82 445.11 0.03 0.03 0.07 154.49 184.16 1.43 2/01/06 11:44:00 4.90 10667.97 64.81 0.06 510.86 445.31 0.03 0.03 0.07 154.49 184.54 1.43 2/n1 /nR 11 45-nn 4.84 _A .88 AA )7 A nf'2 eAl f% An 4CA At% 4fA 4^

IV t. I .

.1 AA I .

2/01/06 11:46:00 4.88 10654.68 64.94 0.06 510.98 445.19 0.03 0.03 -0.02 154.49 184.21 1.43 2/01/06 11:47:00 4.91 10655.47 64.88 0.06 511.17 445.15 0.03 0.03 0.16 154.49 184.40 1.44 2/01/06 11:48:00 4.85 10657.03 64.87 0.06 510.90 445.27 0.03 0.03 0.31 154.49 184.36 1.43 2/01/06 11:49:00 4.85 10652.34 64.92 0.07 511.05 445.27 0.03 0.03 0.46 154.49 184.21 1.43

2/01/06 11:50:00 4.86 10636.72 64.87 0.06 511.06 445.35 0.03 0.03 0.55 154.49 184.07 1.44 2/01/06 11:51:00 4.89 10643.75 64.86 0.07 510.75 445.27 0.03 0.03 0.80 154.49 184.26 1.43 2/01/06 11:52:00 4.76 10660.94 64.76 0.06 510.86 445.23 0.03 0.03 0.74 154.49 184.26 1.44 2/01/06 11:53:00 4.91 10653.91 64.80 0.07 510.82 445.27 0.03 0.03 0.28 154.49 184.26 1.44 2/01/06 11:54:00 4.95 10667.97 64.98 0.06 510.94 445.15 0.03 0.03 0.10 154.49 184.16 1.43 2101/06 11:55:00 4.77 10671.09 64.87 0.06 510.78 445.23 0.03 0.03 -0.22 154.49 183.98 1.43 2/01/06 11:56:00 4.89 10690.63 64.96 0.06 510.78 445.23 0.03 0.03 -0.22 154.49 184.40 1.43 2/01/06 11:57:00 4.88 10649.22 64.85 0.06 510.59 445.11 0.03 0.03 0.16 154.49 184.21 1.43 2/01/06 11:58:00 4.79 10644.53 64.93 0.06 510.90 445.27 0.03 0.03 0.09 154.49 184.12 1.43 2/01/06 11:59:00 4.89 10642.97 64.64 0.06 510.94 445.23 0.03 0.03 0.00 154.49 184.21 1.43 2/01/06 12:00:00 4.79 10657.81 64.82 0.06 510.71 445.31 0.03 0.03 0.03 154.49 184.17 1.43 2/01/06 12:01:00 4.88 10645.31 64.91 0.06 511.09 445.23 0.03 0.03 0.24 154.49 184.16 1.43 2/01/06 12:02:00 4.88 10668.75 64.88 0.06 510.82 445.11 0.03 0.03 0.10 154.49 184.17 1.43 2/01/06 12:03:00 4.77 10663.28 64.76 0.06 511.01 445.23 0.03 0.03 -0.29 154.49 184.21 1.43 2/01/06 12:04:00 4.75 10649.22 64.79 0.06 510.90 445.27 0.03 0.03 -0.17 154.49 184.07 1.43 2/01/06 12:05:00 4.90 10628.90 64.90 0.06 510.86 445.31 0.03 0.03 -0.07 154.49 184.17 1.44 2/01/06 12:06:00 4.86 10642.97 64.84 0.07 510.94 445.39 0.03 0.03 -0.07 154.49 184.21 1.44 2/1106 12:07:00 A4.85 10665.62 64.93 0.06 510.67 445.19 0.03 0.03 0.30 154.49 184.12 1.44 2/01/06 12:08:00 4.83 10670.31 64.74 0.06 510.97 445.27 0.03 0.03 0.23 154.49 184.21 1.43 2/01/06 12:09:00 4.79 10650.78 64.87 0.06 511.09 445.31 0.03 0.03 0.33 154.49 184.02 1.43 2/01/06 12:10:00 4.86 10633.59 64.94 0.06 510.82 445.43 0.03 0.03 0.27 154.49 183.98 1.44 2/01/06 12:11:00 4.79 10642.97 64.94 0.06 510.90 445.19 0.03 0.03 0.18 154.49 184.07 1.43 2/01/06 12:12:00 4.87 10696.87 64.79 0.06 510.94 445.23 0.03 0.03 0.06 154.49 184.12 1.43 2/01/06 12:13:00 4.81 10671.09 64.87 0.06 510.78 445.15 0.03 0.03 -0.25 154.49 183.98 1.43 2/01/06 12:14:00 4.81 10658.59 64.80 0.06 510.98 445.35 0.03 0.03 -0.20 154.49 183.98 1.44 2/01/06 12:15:00 4.82 10642.19 64.87 0.07 510.94 445.31 0.03 0.03 0.04 154.49 184.26 1.44 2/01/06 12:16:00 4.80 10667.97 64.88 0.06 510.67 445.19 0.03 0.03 0.07 154.49 184.45 1.43 2/01/06 12:17:00 4.87 10636.72 64.87 0.06 511.13 445.27 0.03 0.03 0.09 154.49 184.16 1.43 2/01/06 12:18:00 4.80 10667.97 64.91 0.06 510.82 445.27 0.03 0.03 -0.18 154.49 184.26 1.43 2/01/06 12:19:00 4.80 10643.75 65.06 0.06 510.82 445.19 0.03 0.03 -0.09 154.49 184.16 1.43 2/01/06 12:20:00 4.82 10650.00 64.93 0.06 510.94 445.31 0.03 0.03 0.07 154.49 184.03 1.44 2/01/06 12:21:00 4.91 10666.41 64.84 0.06 510.86 445.23 0.03 0.03 0.07 154.49 184.17 1.43

Open .xls from R*Time Highlight Cell Al R*Time Archive Date Parameters (4037 for 14 days @ 1200)

SJAE Off-Gas Act (BOPM002) 5.00 -

4.95 -

4.70 4.65 -

i- - -

SJAE Steam Flow (T032) a

? g? §to9-In §g F ggRF gR .n §? ?.

ii 03 9 ? -eR .0 R8 ?T: gR"i

.i

V R 9 v v v v

RWCU Flow (3DMAO09) fiS.10 65.05 65.00 r 64.00 IIII I IN 164.90A55 A A 64.f0i 04.78 64.7 64.65:

64.60 63 p~~ ~~ N e .< >a .. e$ , - N RWCU Flow (COO9) 0.07 0.07 0.06 h2 AAB O.O AMA/ IN AA I

l A Vvl\

a 0.06 0.06 O.OB .-.

O

$l$$ e IR o e e. $ E $8 $8,p RWCU Inlet Temp (B023) 511.30 51120 511.10- A 511.00 A I- I A.A A1 AI 510.70 510.60 510.50 510.40 510.30 -

.8. 8I _ _ _ _ _ - _ N NN N N

RWCU Outlet lemp (B024) 445.60 445.50 445340 445.320 445.10 445.00 v 444.90 444.80 444.70 eD _,

A- RWCU Demin Flow (B017) 0.03 0.03 0.03 0.03 e 8. S2 . e.. . . . 2 i l i 4 B - RWCU Demin Flow (B018) 0.03 0.03 0.03 0.03 0.03K V __

0.03 0.03 0.03 0.03 4n i3qO~o q0

RWCU Inlet Temip ROC (C039)

U.

RWCU Pump Flow (B054) 1wi.IA .

I

~ - v- -p -

RWCU Regen HX Outlet Temp (B055) 184.80 184.'40 A AA LL 184.20 184.00 183.80 -

183.60 0 °0 09 -1 9

RWCU Loop Thermal Power (BOP014)

II.4 1.43 1.42

-f 2E fiE ~ -$g -f g8 ff f S~~~~ . &8 ~

Ot NC Is O 4

VYNPS EPU Power Ascension Testing Feedwater Control System Monitoring Plan (2 pages)

sy-St N EPU Steady-State Nominal Operating Conditions I

PlSetmPr.MM~[Ufl I I[.I .r II - II CU I n I C -m*- I V L INCL - I CPU TP I CLlP -I N Imu IU . 9 CLTPr 6 - ... IIl E -

lI CIIPN Ie..

IcLTP IIpu - I ... S -Il- IC I CLTPL Iur lIP . . lN CO00 Ie k PMpdai 6 4 4- > ALERT cc 4I >> ALERT cc 6 cALERTcc 4.

F I ,..ALERTc.c I

.1 ,..ALERTc< 1 ..>ALER'rc.c 1 > ALERT cc I 6.475 S.475 6.475

&.475 >o. ALERT cc

>>ALERT <cc >, ALERT<>ALERT <- ~~-ALRT >> ALERTH , ALERT <-c sonmb XITM onbo Loop SC StIMM cW Predlced 1.016 1.615 1.660 1.755 1.75 1.766

-cI > AE"ac 1.41

1. >AET 1.606 1.90 1.677 SOC8 14)-7 BM5 LcopBICSbml FIDW Pb 1.615~~~>
Act/uMM"W-14)1.615 1.8tc 165 Ac~~~~~~~~d 1.615 J1.0 .
>ALR
>> ALERT -cc e
1.fi cc>AET<>ART ALERT c<
.70 >, ALERT <c t753 .>>>AL ALERTERT<<
t798
<c >>>> ALERTT.*
ALERT c< ~> >>,LRTc 1 ALERT cc 5g87 t.9
>ALERTc
>, ALERT cc 2.2 "AER
>, ALERT <c 12.Ml 6664 Tlop D d st. b. P.F 1.660 SAM0 W1.70 1J85 t" 0067 8 -/q1.017 _ .699 t1640 1.9TA 1.677 2.022 2.078 1.699 >> ALERTcee >>ALERTc << > ALERT cc >> ALERT cc s.>ALERT cc >>. ALERT cc >, ALE3RT cc ,, ALERT cc CO~ Tob~lPF.dFw[I _0. Plede 340 6)30 68Jtl 7927 650 7.t54 7.23 71.81 7.697 7.878
)Adia 6.448 6.448 ,. ALERT << >ALERT cc >> ALERT << >> ALERT cc >> ALERT cc >> ALERT ce >, ALERT c >> ALERT <<
LoopA F.. FlowMelI Pr 3.264 a 6 316 a 446 &)36 &)21 3.723 0.615 a 7
(* 3)
A 3264 3.6 >> AALERT ALERTcc <c >,> AL <ER >> ALERT <c >> ALERT c< >> ALERT << >> ALERT <c >> ALERT <<
- ep . . m.. PpwddM tile 3.186 2.279 . w =24 &9 ffi.0,j ia091 A'Pd 185 3te 3.185 >> ALERT cc >> ALERT << >> ALERT << >> ALERT <c >: ALERT _c >,. ALERT << >> ALERT << >> ALERT <c AFOt (VO) D--W M Prldlcted 4619 420 45.25 4M fO 51.75 G&Wo.25 61.0 64.75 66M p6(3hcprpbselb) AMMd 48.48 >> ALERT cc >> ALERT << 48.48 >> ALERT cc >> ALERT c< >> ALERT c< >> ALERT << >, ALERT c< ,> ALERT <<
061 s Fed CW) Dont 1 Preditd 4__ 42w 4y25 46. 51.75 655 w.2 10 WS4.75 c.wo M3 &) Ad 48.51 >> ALERTc >ALERT c-c 48.51 >> ALERT c< >>'ALERT < 3.ALERT c< >> ALERT< >> ALERT c< >>ALERT4-c 602 FRVA Stem F 1) Pedld 450s 42.00 4a. 4So 51.76 60.00 65.25 S1.D "T7o 56.00 AcBPed 47.83 >> ALERT c< ALERT << 47.83 >> AALERT >ALERT <c >> ALERT c >>ALERTc ,>ALERT c ,'>ALERT 5a6 FRV 8* Sbtu P x Prdded 40.50 42.o 4828 - 4x 01.75 s61 6026 (3hed pmnpwbvef**) ACkd 61.50 6470 e8.00 47.50 >> ALERT<.c >>,ALERT <c 47.50 >>ALERTc< >>ALERT--- ,ALERTcc >2ALERTcc >>ALERT ,>ALERT<C
'-AL PREDICTED DATA ASSUMES UIM5ER HE 0ATIHBE6WI JWANO62-WDeReowdadBy/ Mft DM Rerrded By I Dae 1673 MWlh 1762 MWth (67.5% EPU) (91.6%EPU)
DabRoAlced By/ Def -a I d .v I -a Dab RecededByI DIM -- -1 1832 MWOI 1912 MWrh (9"% ES (160.§%EP )
Nh Ray Rl,I is
. a +l1. ; . .+.. .i. :SM. = -. ..
p.0.So lyOoNm:
Ils-Cod:
37N9SEVMOM JAMItlfM PMMOMoo F-.A.4oePFo. COw30 FWC Sst-o I
PodbOm004EoaIs1I~df~j a V. Sydm FftfhR~paEfg e.Io.d-~drp 1 02-M P 2aai2 1T16046126" Is3!0 la: l. d4 01127106 Aprvd R.~I PEND0INGO(Rw NNE14.
0.1we Jwm.2004)
CDPF4MWpifi06L siflgl*4a00100611.W KrG jOPL41I2 1 I gluM OI 5 --
System Punctlor:
512 MR04 UR-4 MR-S Pm1044.3bohR..ybwomlm,4o.MR. W0k01. 0 6 P.o.ld.t,. 0 P00M...
WSmeo R~.
y09t000 G
0MIy kpA hp 7lrW P-dP.ot-
.4O.Ww*
m .- bilym. -t A- .,0IIOIyW dE~-h..e6~odg dal;bommA n
4 p4 I
Pk%I) P4.4.
SYII YN . MRW.1000.412 N.2A T U E.U%13.74piod MR.A. Sompkb 30.4 SYTEM s- N. MR.. 1101Wlky WA T U 3 M29F.1-y..p.W od 51 S. Sod.
STEAMPLOW?P M-I.~~7. ERAIS w-RAMPIFOUIERS QUR P744143,,71D Y.. Sb Fb. FTP.-1 200MoLft 1C430 10051 LOOPS A 71IRUG 80041 Adg ERASPSAAN06 em6, WIG p.oq ERPSF 1sdM 4 Sp~p~t~
FEEDWATERLOW_
FoodRoW ER W, V FLIP, -1.A10 MbftQ 1013esCo. 7.00.M.400.
FT410I10~ld ToWESSOAE headl R- coal1 IC'J34560. 61 1. k4 Wlw S1EAIOPLOWJ-ED PERFIS 07 FLOWERROR r-PAA44.74 V". 3tnwFtR 5az cool; MfT 006 600.0 OM b. T..d4.~ P0S VEWEIATERLM oI" 04.10. 70: ERF5 W 00W 106-165bt44. 0RIS075d..
?P TRANSMITTERS: LT474OAff2n Y". Ch.0.4.A00d 3 15041.1742 a CHANNEL0SAA4D403 3LAETRO FA--0 " I01I0D06Wt-PI- ASR0.5IS07 RIOW m" ~ C.1o. T.Wd 44.ASS AMPLIFIE 0 S"P97064-154 k100N . 0061 MASTER WAlER LC-443 Y"0 MP.Wd FlWD.oooi I LIT ol 3000 ERFX C b. TrW4.d FISS LEVELCOTO40.LLER Saw2.3061 9074003I2.WATER O 60640.0~dV 91F9S wrDw cp-, 00 w RIP0071TI9NER: AaVd,06VOS4.0P0600. E01R0 JCLTR 47% 100%.P 11- P-oo)
LWAN, WP4-&mAgI= V..R. AWRVB gW.-421@ I001 (OS~I 0IS Coob.T-.02004.P AM.. L.t &.t514.7o R.p*.oo.00 A44. 90.405 904.2 P-km.inkwk-bWh, "N.&Sw3 0110000 5100.g0 rEPU PoO.Ae-..bbudS V~~d~,1t1~t ,fm %ttEUP A,61 R2~01~~
d2' m\ o44 o -r10Sy~o P.16,- -M o.MoboIM ERi - WEIIY.Sy~ or2I~i,(2 NVY W.F C Sy~ aad.
US eB.i
VYNPS EPU Power Ascension Testing Nuclear Boiler System Monitoring Plan (2 pages)
Equipment Equipment Pam Alert and Action Actions 1593 1673 1752 1832 1912 Name No.IID ID Action iLeve Required Reason or MwTh MwTh MwTh MwTh MwTh Parameter Source F Level other info
-SOOO S00I Recbrii Motor -
S002,S003 continuously / Alarms at MG Set Motor and S004,S005 Incorporate 220F, Gen High temp Generator Winding dats Into xbs alarms at degrades Recirc MG Set MG-1-1AtB Temperatures S006,S007 ERFIS and 240F -raPh Evaluate Insulation -
continuously High temp MG Set Motor and incorporate indicates Generator Bearing data Into xh Alarms at bearing Recirc MG Set MG-1-1A/B Temperatures S035-SO0O ERFIS and graph 16OF Level 4 Evaluate degradation Rewordria _
continuously I Incorporate dais intoxb Copareto Recirc MG Set MG-I-AIB ibration NIA AP4211 ano graph baseiino Levei4 Evaluate 13asefilneT -
1593 MWth, Reworded Continuously.
Incorporate Compare to Recirc MG Set MG-1 -1A/B Thermography N/A AP-0211 Data Into DB baseline Level 4 Evaluate continuously!
incrporate Recirc Pump data Into xs Per DP-Motors P-I-1A/B vibration N/A AP21 andgraph 0211 Level 4 Evaluate Recorded continuously/
incrorate Recirc Pump Winding data Into xs Motors P-18-IA/B Temperature N/A ERFIS and graph 21eF Level 4 Evaluate BaSellneO (g -- - -
1593 MWth, Recorded Contiruosly, Recirc Pump Bearing Incorporate Motors P-18-1A/B Temperature NA ERFIS DaaintoDB OOF Level 4 Evaluate
_ Recordrea continuouslyr incorporeht sl lRecircPumps lP-1I AIB Seal Stage Pressures WNA
- fTM2003- Idata kiot alaI 023 ani graph lDeviation I Level 4 I
Evaluate I I I J 1 Recirc Pumps l
l P-18-IA/B l
l l
Seal Stage Temperatures l
l IN/A jl
§ ERFIS lcontinuously l lin~~~corporate data into x)s l anid graph l1OF l _______
Level 4 Evaluate
.. . I..
Per Jet Pumps A-K, L-W Pump dP IN/A OP-4110 IDeaiy arocedure Level 4 Evaluate
_E 17950 -
The N-ratio of a jet pump is its a tion flow his is divided Propoaed byr its add to OP Per drivre Jet Pumps A- L-W M-ratio N/A 4110 Dail Procedure Level 4 Evaluate ow.
. - - :valuate I Talpipe Per OP- repair I SRVa Tailpipe Temp Baseline Dt ERFIS ContInuous 2122 Level 4 rebaseline Uaiiy .
Pressure Drywell Unidentified (recorded 4 Per tech Per tech Boundary Leakage N/A OP 4152 times daily pec Level 4 spec Steam Dryer _ Moisture Carryover N/A Sample Per STP Attach 4 Level 2 Change I from j GESIL 644 Steam Dryer I Dryer Failure Numerous ERFIS ON 3178 baseine Level 4 InVet SU 0 0 o- ___PC from AOG Recomab 02 ICP-HWVC-5 02%6 >10% to <18% OP 0150 OP 21D9 baseline Level 4 IEvakiate.
1673 MwTh Data Recorded By_ Date:
1673 MwTh Data Reviewed By r Date: _ _
1752 MwTh Data Recorded By. . . Date:___
1752 MwTh Data Reviewed By- ..- Date: _ _
1832 MwTh Data Recorded By:_ Date: _ _
1832 MwTh Data Reviewed By_ _. Date:
1912 MwTh Data Recorded By_ _ Date: _ _
1912 MwTh Data Reviewed By___ Date: _ _
NB EPU Performance Monitorina Plan
VYNPS EPU Power Ascension Testing HVAC System Monitoring Plan (2 pages)
EPU Supplemental Performance Monitoring Plan for the HVAC System Increased Power Level Evaluation Points Previously Equipment No. Parameter Alarm Level 1593 MaWh 1673 MWth 1752 MWth 1832 MWth 1912 MWth Source MonItored 3-FDWValues/imis 3.FDW/ (87.48%) (91.65%) (95.8o) (100%)
2 Computer DW Average Temp < 135 OF 4 VYOPF 4115.05 Points elevation 250' <
10 Computer DW Average Temp < 150 OF 4 VYOPF 4115.05 Points below elevation 270' 6 Computer DW Average Temp < 185 OF 4 VYOPF 4115.05 Points elevation 270' to 315'
_ 4 Computer DW Average Temp 2OPF 4115.05
__________ Points above elevation 315' <270 OF 4 MN STM Steam Tunnel Temp < 160 F 4 VM-1 2-1 X 126A HPCSteam Tunnelm <160 °F 4 VM9-21 HPCI TE HPCI Steam Tunnel < O .. VM-12-1 105A Temp <175 F 4 CRP 9-21 x HPCI TE 105B HPCI Steam Tunnel Temp
< 175 OF 4VM-1 2-1
__ _ _ _ _ _ _ _ _ __ _ _ _ _ CRP 9-21 RCIC TE-13-77A RCIC Steam Tunnel < 175 OF 4 VM-12-1 Raveragetem Thermoreter TB Rm B-3 Cond Pumps Room < 105 °F 4 H Held average temp Thermometer EPU PATP - HVAC Monitoring 02/25/2006 Page 1 of 2
EPU Supplemental Performance Monitoring Plan for the HVAC System 1593 MWth Data Recorded By: Date:
1593 MWth Data Reviewed By: Date:
1673 MWth Data Recorded By: Date:
1673 MWth Data Reviewed By: Date:
1752 MWth Data Recorded By: Date:
1752 MWth Data Reviewed By: Date:
1832 MWth Data Recorded By: Date:
1832 MWth Data Reviewed By: Date:
i9i2 Mvivvh Data Recorded By: Date:
1912 MWth Data Reviewed By: Date:
EPU PATP - HVAC Monitoring 02/25/2006 Page 2 of 2
VYNPS EPU Power Ascension Testing Motors Monitoring Plan (25 pages)
Pow., upr.t PowtAcmidon Too"~n PerforvmwooM.dwbu" Plan 12 1 9 7 4~912 49%
8.96 9 SI 833%
~Th8 Ca. ~ Tm.
Dal j~i. ~Oat.1 880%100 jh Dote:
v
FIqO JM/AISO1017R12Le.
ey680VAog MAWM.
Vi..I In.pt Coft E.ohPo.o5I f leVcin ~ ~ p C(tIEngeor , dP., CMS. Ewko% me.1 20100n ViSnMob AP'0211 CWl2110, Esoh Polw CE E'Id.1owolo fn 2120 hold pWb oU,h10 ..odioo VA.l-ton.Pwo.P AP 0211Cal21 10, E.ch Pow[*.Ilol C Ew9..b. PumV (Via 2120 hold Ooin CE___ _ ________d__
T h.nnog.phy Th.-nglsphy Eooh Po,,I. lI CE HQotsoft ln"SObt. 0 of upp., Owi~ng T"o ERFIS P50(9 E..h PoMKM we 7 (1S0) D0. FImogb (B-To.P) 5067, 5089. E071 hold 50.1K CE 1S(110,..,,2D Imol C. o A E057__ _ _ _ _
B Fogg_ __ _ __ _
Lowr b..rlng TornV (B.ToMP)
ERM'S Pobto E09 7,07 ~
E~ohPowr I.-
p~t CE 1SO(190) Dog FI (172CM0)EPUJ200
-io
~"
A I 5068 B E070_ _ _ _ _ _ __ _ _
WlodoogTootpo 5I~IB 501. sot, Pow, jowl100(100) 'dogC otbt aog
)W-TOMP) 5029,5020,5021 h.pold II.5 A E031 _ _ _ _ _ _ _ _ _ _ I__
B 5030 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
CE031 _ _ _ _ _ _ _ _ _ _ _ _
EquipmentSttle. Eogr..V IE'EwkmI eroicgiW MOW.,*.
. POOR W MIMIw Colonwol 0 U .. -. 1 .1. I. :... .~I . ; 1-o -~
a P.iit!rC 6"a k II

_11____

m~b
-o.1 Motor Engk~uw
,~tM _,glnw I -
UppB, n..ngTdgp ERFIS PibW07B3, RA.x174 dogFGIf i dE (B-Th.p) WV075,W077 lki CIfdtFF bm A W077 B W075 C W077 1-lb."Temp ERFISPolxfti74, Fan17t (8-Temp) W07ti,W07S L.. por 9de CE Abmm1e4dotF 81CInD u A W074 7 b m B W076 _
W078 Equl.nur Stntus I gE.i.h.V I Led POM Inst MotarCEEk M O P=iB S t I JodgetsIA __ _ _ _ 1_D.
ldp~o IE~~~~~~~~~~dwfr _ Mb 5111s EE _ _ _ _ _ _ ~ siE ont r0,i .lr on __ ___ _
. ..... I.-..-
a ,I .. . : . 1. ......
Vib.l Inetbr SE,CE Eholdorlne MdlL E CEe 6(r) E*oe Vbmonto AP 0211 CSI 2115, Esoh PFr lbwl Ewhmw 01008 (VI) 2120 hold potot byorb erdlbon A
A B _ __ _ _ ___
DC ERFIS Pokos WntdingT mp, A: F070. F071. F072 E-eh PowN o.. CE 220 degF ig d (W-T.MP) C: F0SY4FOOS FOOS D: FP01.F062. F053 A A:F070 A A: F071 A A:P072__ _ _ _ _ __ _ _ _ ___ _ _ _ _
B B:PF04 _ _ _ = _.
B B:F060 __ ___ _ _ _
B S:F06 _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _
C C: F0_7 C C!F006 _ .
C C:F06 _ _ _ __ _ _ _ _ _ _ _ _ _
D D.FOtl1 D DF0,2 _ _ _
D 06 D F0_3 PwFr Arp..g. OP 0150 SE ' 32 A." Es., moeor B _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ _ _ __ _ __
Equipionst AaELu-Statw SbulL.
[l Erngbooahng EachPwrhost J bm r holdtook l r Uco MOO E @I E
I__n_
w o i_ l__ _________
Connonto
I v~IIn - Il Ill I. SE.CE tat Po1-r eIlMlut. E,CE.SEOp_
Eq St.W. IEngknwig LJsIP 1 rCE IEquip.srmr)IJudunnte ..
FAIRMOMMM 03.73%riff-,W"-&VA Fmq--y
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.h
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AbrVAd-AINVAdi..
220 "od-Fl" E"kisk d-9 ESkm%
dgF.F Urn
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ho 'Imp candklon bo" wMP am was come
=la wmw I-W m"Ir RK'n of of I WERM 1833190410mmm I01, ImPORW- ---- 97.is ::,.,Kurzweil-.
Dt.: OmI
I I -- I - I1 IVoualInpodio CE, SE Periodlc Mat. E, CESE.ops Eqipm..nt Sttes Englnilogn Lj Po r L I MtorCE I(EquiP. St..) Judg.-m I
Entergy Nuclear - Vermont Yankee Performance Parameter Spreadsheet Component Type: Motors Component Engineer: Chris Kowal
(AssignedCoor)

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VYNPS EPU Power Ascension Testing Service Water System Monitoring Plan a
(4 pages)
EPU Supplemental Performance Monitoring Plan for the SW System
_ I Increased Power Level Evaluation Points Previously Alarm eWth 153 1673 MWth 11752 MWth 1912 MWth Monitored Equipment No. Parameter Values/Limits Level Pre PA Activity (83.32%) (87.48%) (91.65%) (100%) Source Number of Pumps 2 during Record # of 3 Pumps 3 Pumps 3 Pumps 3 Pumps ERFIS - E516, P-7-IA-D Running Feb/lMar 2 Pumps Running Running Running Running E517, E518, E519 Record Pressure Pressure Pressure Pressure OP 0150.03 P-1_04_20A/B SW Header Pressure 97-117 psig 2 Header < 97 psig < 97 psig < 97 psig c 97 psig CRP 9-6 X RD-I7-332 SW Rad Monitor Flow 1.0(Note
- 2.0 gpm
___RD_17_332 S RaMoirFlw 2) 3 Record Flow >2Flow gpm > 2Flow gpm > Flow p > Flow 2 gpm OP 0150.05 Fl-I104-332 X P-7-1A Running Amps 32 2 Record Amps Amps Amps Amps Amps OP 0150.03
_____ (Note 2) 31 31 31 > 31 CRP9-6 X P-7-1 B Running Amps 32 2 Rvecrd Amps Amps Amps Amps Amps OP 0150.03
___ _ _ __ _ _(Note 2) _ _ _ __ 31 31 31 > 31 CRP 9-6 X P-IRunnAms32 Record Amps Amps Amps Amps Amps OP 0150.03
______(Note 2) 3131 31 > 31 CRP 9-6 X P-7-1 D Running Amps Note 2 3Nte2 2 Record Amps Amps 31 1 Amps 31 Amps 31 Amps
>31 OP 0150.03 CRP 9-6 X P-7-1A-D Motor Winding Temp Monitored by Components E-10-1A-D H2 Temp Monitored by Turbine Generator Program E-25-1A&B TLO Outlet Temp Monitored by Turbine Generator Program E-26-.A&B SC Outlet Temp Monitored by Turbine Generator Program Alterex Temp Monitored by Turbine Generator Program TRU-5 Condensate Pump Monitored by HVAC Program TRU-1,2,3,4 Feed Pump Room Monitored by HVAC Program RRU-17A&B Steam Tunnel Temp_ Monitored by HVAC Program TCV-1t04-20 TCI0-0H olrOte H2 Cooler Outlet I
N/A l 2 IRecord Valve lmo Pntinnl 75% Open III75% Open l 75% Open l 75% Open TCV-104-20 TCV-104-21 TLO Cooler Outlet N/A 2 StecmorVatlvoe 75% Open 75% Open 75% Open 75% Open TCV-104-21 lX lE-22-1A&B l(TBCCW Outlet Templ (TBCCW not SW)
< 100 OF (Note 3) 3Temp Record Outlet >g5o F
>_9_______ __
>950 F l95
_ >95 F
>950 F 950_ __
F ERFIS-MO42
_______-_M042 02/2512006
EPU Supplemental Performance Monitoring Plan for the SW System Increased Power Level Evaluation Points J Previously Alarm 1593MWth 1673MWth 1752 MWth 1912MWth Monitored Eaubment No. Parameter Values/Limits Level Pre PA Activity (83.32%) (87.48%) (91.65%) (100%) Source TCV-104-3 "A"TBCCW HX Outet N/A 3 RStem Position 75% Open 75% Open 75% Open 75% Open TCV-1 04-3 TCV-104-6 "B"TBCCW HX Outlet N/A 3 Stem Position 75% Open 75% Open 75% Open 75% Open TCV-104-6 X E-8-1A RBCCW Outlet Temp <100 F Record Outlet > 95° F > 95° F > 95° F > 950 F ERFIS - M008 (RBCCW not SW) (Note 3) Temp X E-8-1 B RBCCW Outlet Temp, < 100 OF 3 Record Outlet > 950 F > 950 F > 950 F > 950 F ERFIS - M009 (RBCCW not SW) (Note 3) Temp "A"MGLO Outlet <10'FRcrOultERFIS - W082 I lE40-1A T p(!Oil not SW 3 >er>130 F >1300 F > 1300 F > 130" F ODMI CR-VTY-X ATemp lE40-1B (Oil not SW Na 2)40 F l_______
3_ 10F 13Fl 3Fl 30 I2005-02391
[ X E40-11B B" MGLO Outlet Temp (Oil not SW
<j4 FRcr (N1402"F Reodute ultERFIS
> 130" F
___O__l
- W085
> 1300 F > 130" F > 1300 F ODMI CR-VTY-I________
p(N _ _ _ oe 2
_ _ _ _ _ _ Te m Te p _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2005-0 2391 Note 3 - From USFAR/TS Note 2 - From Procedure or Alarm Set Point Note 1 - Based on Review of Trending Data Manual adjustment of valve positions to control flow/temperature must be recorded Prepared by: Date Reviewed by: Date 02/25/2006
SW EPU Monitonng Logs l Alarm l l Increased Power Level Evaluation Points t Equipment No. Parameter Values/Limits Level 1593 MWth 1673 MVth 1752 MWth 1832 MWth 1912 MWth Source P-7-1A-D Number of Pumps > 2 during 2 2 Pumps ERFIS - E516, Running Feb/Mar Running . _._. ___E517, E518, E519 Pl-104-20A/B SW Header Pressure 97-117 psig 2 Pressure OCRP 9-6 RD-17-332 SW Rad Monitor Flow 1.0 - 2.0 gpm 3 < F2lowm F-1 04-332 P-7-1A Running Amps 32 2 < 31 OP 0150.03 p____
7-1_Bunigmp23
_ CRP 9-6 P-7-1 B Running Amps 32 2 < 31 OP 0150.03
_____ _ __ ____CRP 9-6 P-7-1 C Running Amps 32 2 < 31 CRP
_ OP 019-6 50.03 P-7-1 D Running Amps 32 2 < 31 OP 01 50.03
__ __ _ _ _ __ _ _ __ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _C R PD9-6 TCV-1 04-20 H2 Cooler Outlet N/A 2 <75% Open TCV-104-20 TCV-1 04-21 TLO Cooler Outlet N/A 2 <75% Open TCV-104-21 E-22-1A&B TBCCW Outlet Temp < 100 OF 3 < 950 F ERFIS - M042 (TCWnot SW)
TCV-1 04-3 "A"TBCCW HX Outlet N/A 3 < 75% TCV-1 04-3 TCV-104-6 "B" TBCCW HX Outlet N/A 3 < 75% TCV-104-6
. Open E-8-1A RBCCW Outlet Temp < 100 °F 3 < 950 F ERFIS - M008 (RBCCW not SW)
E-8-1 B RBCCW Outlet Temp < 100 OF 3 < 950 F ERFIS - M009 (RBCCW not SW)
E40-IA "A" MGLO Outlet Temp (Oil not SW < 140 OF 3 < 1300 F J 1 ERFIS - W082 IODMI CR-VTY-Temp) I I200502391
SW EPU Monitorng Logs 1 Alarm Increased Power Level Evaluation Points Equipment No. Parameter Values/Limits Level 1593 MW 1673 th MWth 1752 MWth 1832 MW 1912 th MWth Source kBH MGLO Outlet 1 1 _ ERFIS - W085 E40-1B Temp (Oil not SW < 140 F 3 < 1300 F ODMI CR-VTY-Temp 2005-02391 1673 MWth Data Recorded By. Date:
1673 MWth Data Reviewed By: Date:
1752 MWth Data Recorded By. Date:
1752 MWth Data Reviewed By: Date:
1832 MWth Data Recorded By: Date:
1832 MWth Data Reviewed By: Date:
1912 MWth Data Recorded By. Date:
1912 MWth Data Reviewed By: _ _
Date:
VYNPS EPU Power Ascension Testing Turbine Generator System Monitoring Plan (6 pages)
System Name: Stator Cooling Date Issued: System Functions: MR-1 Provide cooling for the main generator System Code: SC MR-2 Provide necessary instrumentation to allow for identification of System Engineer: Bob Swanson operational status.
MR-3 Provide necessary signals to initate a timed turbine trip System Performance Goals/lndicator:
SCW P&ID Click Here Equipment Name Equipment NoJID Critical Parameter Instrument MIT Freq Acceptance Bands Source Reason or other Info TG-1-1A STEAM TURBINE Generator MWe GENERATOR UNIT Yes ERFIS G002 MIT D -550 MWE ERFIS Can be Trended via PSS.
TG-1 -1A STEAM TURBINE Stator Cooling GENERATOR UNIT Yes d DPInze 1110-YGA-6 T 0 *14 psid OP 0105 TG-1-1A STEAM TURBINE Stator Coolina T GENERATOR UNIT Yes Eilter dP DPI-1 10-YGA4 T D <9 psid OP 0105 TG-1-1A STEAM TURBINE Stator Winding GENER IOR UiT Yes Inlet ERFIS G021 T D - 40 Deg C ERFIS Can be Trended via PSS.
Temnerature TG-1-1A STEAM TURBINE Stator Winding GENERATOR UNIT Yes nlet Pressure Pl-l 10-YGA-2 T D 34-38 psig OP 0105 TG-1-1A STEAM TURBINE Stator Winding FIS-I 0-YFL-l T D 274-288gpm OP 0105 GENERATOR UNIT Yes Ccgolat Flow _IS-10_YL_1T___74_28_______10 TG-1-1A STEAM TURBINE Generator GENERATOR UNIT Yes Outlet CDPR-110-1,pL T D <0.3 pmho/cm OP 0105 ConductivitvY 3_
TG-1-1A STEAM TURBINE Delonizer GENERATOR UNIT Yes Outlet D
____ _Conductivity . .
TG-1-1A STEAM TURBINE Yes H2 Puritn ERFIS G00t M D > 95% ERFIS Can be Trended via PSS.
TG-1-1A STEAM TURBINE Machine Gas ERFIS MIT 30-50C OP 0105 Can be Trended vla PSS.
GENERATOR UNIT Yes l____ D 0-450 _PlI052SS0 TG-'i-iA b I kAM IURBINE IMachine Gas 'M TD a eTeddvia PSS.
GENERATOR UNIT Yes Irs re ERFIS G010 -45IsT EFI R9525 TG-1-1A STEAM TURBINE IGENERATOR UNIT Yes H2 Usage FT-1 10-H-I T D - .277 scfm IOP0105
_______________ - .L -L
System Name: Turbine Lube Oil Date Issued: System Functions: MR-1 Provide lube oil for lubrication of the main turbine.
System Code: TLO MR-2 Provide sufficient oil pressure for control of MS system turbine control and turbine bypass valves System Engineer Bob Swanson and other MHC eqtipmeni MR3PoiefresgnTCpowered lube oil supply System Performance Goals/lndicatorn TLO P&ID Click Here Equipment Name Equipment NoJID Critical Parameter Instrument MIT Freq Accept-co Bans Source Reason or other Info TG-1-1A Turbine Lube OTlCooler ye _ i1 oolrTm tm140 _l TYTbL ees Turbine Oil to Cooler Tem perature T024 TD_30- 40 _ RFI TG-1-1A Turbine Lube lT 110-120 ERFIS SEMTUBN Yes1 Turbine Oil from Cooler Temperature T025 T D II l2 RI TG-1-1A STEAM TURBINE_
GENERATOR UNIT Yes Turbine Bmg Oil Pressure W008 T 0 20-30 ERFIS TB-1 High Pressure Turbine Yea T 0 10/15/35 dog Diff ERFIS Yes Turbine Bmg 2 Oil Outlet W012 T 0 10 / 15 /35 deg Diff ERFIS Oifference between Brg Metal and Oil drain temp TB-1A Low Pressure Turbine Yes Turbine Brag 30Oil Outlet W013 T 0 10 / 15 /35 deg Diff ERFISI Difference between Big Metal and Oil drain tem TB-1A Low Pressure Turbine T Yes Turbine Bmrg Oil Outlet W014 T 0 10/ 15/35 deg Diff ERFIS Diffrence between Brg Metal and Oil drain temp lu-u Low Pressureurbine Yes Turbine Bmg 4 Oil Outet W015 T 0 10 / 15/35 deg Diff ERFIS Difference between Brg Metal and Oil drain temp TB-lB Low Pressure Turbine Yes Bg 60 Oulet W015 T 0 10/15/35 deg Diff ERFIS Difference beween Brg Metaland Oil drain tmp TG-1-1A STEAM TURBINE _ __ _
GENERATOR UNIT Yes Generator Bmg 7 Oil Outlet W017 T D 10 / 15 /35 deg Diff ERFIS Difference between Brg Metal and Oil drain temp TG-1-1A STEAM TURBINE GENERATOR UNIT Yes GeneratorBmg 8011 Outlet W018 T I 10/15/35 degDiff ERFIS Dlfference between Brgi Metal and Oil drain temp Alterrex Exciter Yes Exciter Bmg 9 Oi Outlet W019 T D 10 /15 / 35 deg Diff ERFIS Difference between Brg Metal and Oil drain temp Alt x _Exciter Yes IExciter Bmg 10 Oil Outlet W020 T 0 10/15/35 degDiff ERFIS Difference between Brg Metal and Oll drain temp
System Name: Seal Oil Date Issued: System Functions: MR-1 Provide shaft sealing for the main generator.
System Code: SO System Engineer: Bob Swanson MR-2 Provide for emergency DC powered seal oil supply.
System Performance Goalsalndicator.
SO PMID Click Here Equipment Name Equipment NoJN) Critical Parameter Inebument NMITFreq Acceptance Bands Source Reason or other info TG-1-1A STEAM TURBINE YeT D 451 ERI
_____ _ GENERATOR UNIT Yes Hydrogen Seal Oil Pressure Bearing Woc T D 4551 ERFIS Trending Avaialble In System 1 TG-1-1A STEAM ENRATORTURBINE UNIT Ye Yes Hydgen Seal Oil Pressure Beang W010 T D 452 ERS 452 ERS Trending Avaialble In System 1 TG-1-1A STEAM TURBINE D 8 PSID ERFI I GENERATOR UNIT Ye keal OilI/Gas Pressure Differential lCalculation T 0 8SI) EFS ITrendig Avlalable In System 1
System Name: Turbine Generator )ate Issued: TG System Functions: MR-1 Convert the thermodynamic energy of steam to provide electrical energy System Code: TG MR-2 Provide automatic and manual controls via both the EPR and the MPR MR-3 Control steam flow end pressure to the turbine to protect the turbine from System Engineer Bob Swanson overpressure or excessive speed MR-4 Provide for automatic turbine generator trip under appropriate conditions MR-6 Provide for automatic and manual control of turbine speed, load, and trip MR-6 Provide for monitoring and control of generator hydrogen (H2) purity and System Performance Goalsllndicator: Main Steam Functions Below MS P&ED Click Here MS Functions __...........
1) Conduct steam provided from the NB system to the main turbine at a controlled pressure during normal operation.
2) Provide a supply of steam to the Extraction Steam (ES) system.
3) Provide a supply ofsteam to the Auxilliazy Steam (AS) system.
4) Provide a supply of steam at a controlled pressure for turbine shaft sealing.
'5) Bypass steam directly to the main condenser to control reactor pressure via automatic and local-manual control.
'6) Control steam flow and pressure to the the main turbine to protect the turbine from overpressure or excessive speed.
7) Provide signal for MSIV closure on low turbine Inlet pressure.
8) Provide skinal for Turbine Trio nn high awha ict hevvl temn got.r h
'9) Provide necessary mechanical support to ensure accomplishment of other safety related functions (i.e., piping Integrity to ensure reactor coolant pressure boundary and containment boundry functions).
Main Turbine Yes Turb/Gen Brng 9 - D c 6 mils I Mil Delta RF Reason or other info TB-1 Vibration Svstem 1 T sE IS Main Turbine Yes TurblGen Bnmg 10 T D < 6 mils, I Mil Delta ERFIS TB-1
_Vibration System I Main Turbine Yes Turb/Gen Front Thrust W021 _ < 130150 deg F TB-Y Oil Outet T D 1 ERFIS Can be Trended via PSS.
Main Turbine Turb/Gen Rear Thrust Oil W022 < 130 10 deg F TB-1 Yes Outlet T D ERFIS Main Turbine Yes Turb/Gen Front Thrust W023 T D < 130,150 deg F ERFIS TB-1 BeaenT Metal Main Turbine Turb/Gen Rear Thrust W024 _ < 130150 deg F TB-1 Yes Bearina Metal T 1 ERFIS Can be Trended vi PSS.
Main Turbine TB-1 Yes Thnrst Bearing Wear Turbine End T D 20. 40 mils ERFIS Main Turbine TB-11 Yes Thrust Bearinq Wear Generator End T D 20 40 mils ERFIS Intercept Valve CIV 1/2 Yes Stoke Time Open StopWatch T 0 OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 1/2 Yes Stroke Time Closed StopWatch T Q OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 314 Yes Stroke Time Open StopWatch T 0 OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 3/4 Yes Stroke Time Closed Stop T Q OP 4160 (10% 20%) OP-4160 I Intercept Valve CIV1 Yes StokeThm Onmn AtnnNaftch T C or 4160'1 2%"A C-__ _ _ _
Intercept Valve CIV I Yes Stroke Time Closed StopWatch TIT t 1010%20% OP-4160 __
Intercept Valve CIV 2 Yes _ Stoke Time Open StoDWatch T Q OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 2 Yes Stroke Time Closed StopWatch T OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 3 Yes Stoke Time Open StopWatch T OP 4160 l10% 20%) OP-4160 Intercept Valve CIV 3 Yes Stroke Time Closed StopWatch T OP 4160 (10% 20%) OP-4160 Intercept Valve CIV 4 Yes Stoke Time Open StopWatch T PQA10 (10% 20%) OP-4160 _ _ _
-W I . . I ~. . - .=
t Valve CIV4 I Yes IStroke Time Cosed T IQ IOP 4160 1 IOP-4160 f t Valve CIV 1 l Yes lStokeTime Oen jT Q OP 4160 (1 IOP-4160 Intervznf Valve
., CIV I rIV2 9 I. Yae V..
IStroke I.
iee- clased Iqftk.t Tlme One
_ T~
_ - ___ Q_ -)P- 4160 (10% 20%) OP-4160
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Intsnt Iee DIL a <CVL VOI§fl -. ___ *1 - -
StooWatch T Q °P 4160 (1 IOP-4160 I
Iterept Valve CIV 3 ;Yes Ske Time Open T 0 OP 4160 (10% 20%0) OP-4160
________ U VTT IllIrT:::: 711 I Intercret Valve CIV 3 Yes Stroke Time Closed T Q OP 4160 (10% 20%Y) O1P-4160 stI -I. p lVri A V-. AtiFTn-n £ -= ^_
1*valVe 1
t. nfis.ek T Q nP1s A sn qL sn2AM M
OP-4160 tValve V,'t CIgV 4 THC Yes [troke Time Closed Id !=
jt4,Watch I IJ I ; h! 'I )
[T Q OP 41 ) OP-4160 Byvass Valves Z-1A-1 Yes Stroke Time Open Q*W-t.-h T ')D A4 ) OP-4160 uvvaull I . I AI - -v -
Bypass Valves Z-1A-1 Yes Stroke Tme Closed ttnWatf.h T 0~ ')P 4160( )OP-4160 Bypass Valves Bypass Valves Z-1 B-2 Z-1 B-2
- Yes Yes Stroke Time Stroke Time Open Closed Q 041601 OPI E OP-4160 T 0 )P 4160 (10% 20n%) OP-4160 Bypass Valves Bypass Valves Z-1A-3 Z-1A-3 Yes Yes Stroke rime Stroke Time OPen I T it Q tOP 4160(10% 20%) OP-4160 Closed T_ 0A OP A_ 4160 (10% 20%) OP-4160 Runas VaIvae Z-1 1A StrkA Tine Ore~n RtonWateh T Q3 4 4Z.' ___________
Bvoass Valves Z-1B-4 _OP-4160 Yes Stroke Time Closed StooWatch T Q DP - _ OP-4160 _ _ _ __ _ _
Bypass Valves Z-1A-5 Yes Stroke Time Open _ OP -4160 _ _ _ _ _ _ _ _ _ _
Bypass Valves Z-lA-5 Yes Stroke Time Closed T Q OP 4160 (10% 20%) flp.4.18O OP4160 Bypass Valves Z-11B-6 Yes Stroke Time Open StooWatch T Q DpI DP-4160 v_
Bypass Valves Z-1 B-6 Yes Stroke Time Closed D)P-AI60 OP~-4-6 Bypass Valves Z-1A-7 Yes Stroke Time Oen T 173 4= 'P AlAn t10'h 9nc1 OP.Aiiin
j. - .1- 4 Bvyass Valves Z-1A-7 Yes Stroke Time Closed StooWatch T Q l0P4460 (1%20%1 OP-4160 Bypass Valves !Z-1B-8 troke T Open ime MioWatch T Q OP Rvas M.
-ie Z va ee s. v--e 7_1 A Q Yv. "' C J~v ke L .;. e1. ^1vS'p;ac iu .j r.yi.- -I- r%....
n vpen T A ID Ma4n (41nA WALn %D-A4IAnl
.. "- WW.C - -VCI - v, .Y, ,- n+/- -.--
Bypass Valves Z-1A-9 Yes Stroke Time Closed StopWatch T Q OP 4160 (10% 20%) OP-4160 Bypass Valves Z-1B-10 Yes Stroke Time Open StopWatch T 0 OP 4160 10% 20%) OP-4160 Bypass Valves Z-1B-10 Yes Stroke Time Closed StG0 T Q0 vP 4160 10% 20%) OP-4160 Alterrex Alterrex Yes TEMP SLOT I T D 5 Dea, 10 dea dev ERFIS Ye ALTERREX EXCITER G026T Alterrex Afterrex es TEMP SLOT 2 T D 5 Dea. 10 dea dev ERFIS AAlterrex lterrex M Lg_.
YesALTERREX EXCITER G027 T _
es TEMP SLOT 3 C 5 Dea, 10 deg dev ERFIS
'Alterrex Alterrex Yes GENERATOR SLOTS G039 - G158 T D 2 deg, 5 deg dev ERFIS sGENERATOR HYD G010 T Generator TG-1-1A es PRESSURE osh D >43. >41 ERFIS Yes HYDROGEN TEMP TO G012 T . 1 Generator TG-1-1A ICOOLER A ID 5 Den, IO deg dev ERFIS Yes HYDROGEN TEMP OUT GO017 T Generator TG-1-1A Ys COOLER A D 5 Deg, 10 deg dev ERFIS Generator TG-1-1A Yes Cooler A Delta Calculation T D 2 deg, 6 deg dev Calculatbcn Ye HFYDROGEN TEMP TO G013 T _ _
Generator TG-1-1A Yes HCOOLERB TEM TOD 5 De0 DeT deg dev ERFIS Yes HYDROGEN TEMP OUT G018 T Generator T('-11A Ie Li IO Et D, IV Deg.Om devEisi iS Generator TG-1-1A Yes CoolerOB Delt Calculation T D 12 dea.5 dea dev Generator TG-1-1A I Yes IHYDROGEN TEMP TO G014 T D S e~~ e d v E FS _ _ _ _ _ _ _ _
_ Ys COOLERC T D DenOdedev lERFIS-Ye HYDROGEN TEMP OUT G019IiI Generator TG-1-1A Yes COOLER C T D 5 Dea, 10 den dev ERFIS Generator TG-1-IA Yes Cooler C Delta 2de, ManT 5dendev I I S
Yes HYDROGENTEMPTO G016 Generator TG-1-1A COOLER D _ _T D 5 Deg. 10 cn day ERFIS Ys HYDROGEN TEMP OUIT G020 _I T ___
Generator TG-1-1A Yes COOLER T T D 5 Den. 10 den dev ERFIS Generator TG-1-IA Yes Cooler D Delta Calculation T D 2 dog, 5 deg dev Stator Coolant Temp _
Generator TG-1-1A Yes T D 2 deg, 5den dev ERFIS
_ ALTERREX AIR OUT G023 T_ D 1 _
Generator TG-1-1A Yes TEMP T D S Deg, 10 deg dev ERFIS ALTERREX AIR IN G024 _
Generator TG-1-1A es TEMP T D 5 Dse,10 deg dev ERFIS Generator TG-1-1A Yes Alterex Air Temp Rise Calculation T D 2 den. 5 deg dev COOLANT TEMP OUT G022 Yes STATOR WINDING T Generator TG-1-1A G022 _ D 5 Deg. 10depdev ERFIS COOLANT TEMP IN G021 Yes STATOR WINDING T Generator TG-1-1A _ G021 _ D 5 Deg. 10 deg dev ERFIS Yes COOLANT TEMP Rise Calculation T Generator TG-1-1A STATOR WINDING ___ D 2 deg, 5 deg dev
_ GEN H2 GAS TEMP C027 T _
Generator TG-1-1A Yes RISE T D 2 deq. 5 _ __RFIS
_dev_
Y GEN HOT GAS C028 T Generator TG-1-1A Yes AVERAGE TEMP T D 5_Deg._10degdev _ERFIS JGenerator JTG-1-1A l YsENE COLDTEMP AVERAGE T I D 16 Dog, t0 den RFAS _
dev lERFIS _ _
BVY 06-019 Docket No. 50-271 Attachment 3 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and FIV Effects Data Acquisition System fbr Steam Dryer Pressure Signals Total number of pages in Attachment 3 (excluding this cover sheet) is 13.
Attachment 3 to BVY 06-019 Docket No. 50-271 Page 1 of 13 Vermont Yankee Nuclear Power Station Data Acquisition System for Steam Dryer Pressure and Accelerometer Signals In Reference 11 Entergy committed to installing 32 additional strain gages (SG) on the main steam piping during the Fall 2005 refueling outage (RFO-25) to enhance the data acquisition system (DAS) and improve the accuracy of the steam dryer measurement system. The improvements in detection accuracy will reduce the measurement uncertainty associated with the acoustic circuit model. The commitment was met through the installation of 48 new strain gages and upgrades to the data acquisition system. Temporary Alteration change number TA-2005-15 R1 installed 48 new strain gages during RFO-25.
The DAS consists of strain gages, instrument cabling located inside the drrwell, and a computer located in the reactor building. There is second data acquisition system in the turbine building to collect accelerometer data from piping in the heater bay area. Both systems are remotely accessed over a local area network thereby minimizing test engineer dose during power ascension testing.
Weldable, 350 ohm, high temperature strain gages with shielded high temperature cables were installed on the outside circumference of each of the four main steam lines inside the drywell at 60 degrees apart from at the locations described in Figure EMEB-B-77-1, Sheet 2 (see Attachment 3 to Reference 1). Installation of 6 strain gauges at each data input location provides for improved assessment of internal pressure. Each strain gage is configured in a quarter bridge arrangement rather than Y2 bridge arrangement. The quarter bridge arrangement and 6 gages provide margin for signal failures. An update to Figure EMEB-B-77-1, Sheet 2 is included in the attached portions of the Temporary Alteration.
The upgrades to the DAS included 16-bit USB Digitizer with a sample rate of 200 kS/s.
mounted in each chassis. Mounting the digitizer in the chassis eliminates noise introduced by the computer. There are 3 DC chassis for the SG signals and 1 AC chassis for the accelerometer signals. The SG chassis noise was eliminated by providing external power to the DC powered fans in the chassis. The Endevco 7703A-100 accelerometer units are each screwed to a mounting block that is strapped to the pipe. The accelerometer signal is routed to a charge converter in the drywell. The charge converter connects to an Endevco power supply located outside the drywell. The accelerometer signals are then routed 1l0 NI voltage conditioning cards then to a 16 bit digitizer. There is one personal computer controlling the 48 strain gages and 31 accelerometers for temporal collection of acceleration and strain data from the drywell.
Strain acquisition software allows for automatic Wheatstone bridge null and calibration prior to each data acquisition. The data acquisition software allows variation in acquisition rate, acquisition period, and voltage span to best define the input signal. The accelerometer circuits are tested with a calibrated shaker to confirm the hardware and software are functioning properly. The data is processed with two software packages-MatLab and LabView-for cross checking results.
' Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 33, Extended Power Uprate -
Response to Request for Additional Information," BVY 05-084, September 14, 2005
Attachment 31o BVY 06-019 Docket No. 50-271 Page 2 of 13 The Labview software will also calculate and plot the power spectral density data for each channel and display this data while running. Batch files have been developed efficiently to process the archived data with MatLab for Engineering evaluation and reporting.
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 APPENDIX 'D' TEMPORARY ALTERATION SKETCHES Page 178 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 VY MAIN STEAM LINES PROPOSED
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PIPE SECTIONt TA 2005-15 APPENDIX D SKETCH 01 Page 179 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main St.~am Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D SK<:ETCH 04 PAGE 1 OF 8 MAIN STEAM LINE 'A' UPPER STRAIN GAGE LOCATION AND 'UTr TEMPLATE Prepared By wed By 2fi Or 13,e 91 _
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Page 187 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D SKETCH 04 PAGE 2 OF 8 MAIN STEAM LINE B' UPPER STRAIN GAGE LOCATION AND "UT' TEMPLATE Prepared By rr 4ga 7 r d R viewed By .J Elev 316:-6' 160030
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Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D Sl<ETCH 04 PAGE 3 OF 8 MAIN STEAM LINE 'C' UPPER STRAIN GAGE LOCATION AND UT" TEMPLATE Prepared By ) eyiewed By 9Ze A o^>#/'ev77 ~J~d/( o Elev 316-6".
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Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D SKETCH 04PAGE 4 OF 8 MAIN STEAM LINE D UPPER STRAIN GAGE LOCATION AND "UT' TEMPLATE Prepared By 1jeviewed By Z375?
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Page 190 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D SKETCH 04 PAGES OF 8 MAIN STEAM LINE 'A' LOWER STRAIN GAGE LOCATION AND 'UT' TEMPLATE Prepared By 4:C.eviewed P By EC Lt' Elev 278- 9 1/2" 45 Elbow SG t7A (Cable 76A1 180°
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Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping ir the Drywell REV-01
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Page 192 of 198
Temporary Alteration 2005-15 Insl:allation of Strain Gages on the Main SlIeam Line Piping in the Drywell REV-Ol TA 2005-15 APPENDIX El SKETCH 04 PAGE 7 OF 8 MAIN STEAM LINE 'C LOWER STRAIN GAGE LOCATION AND -UT- TEMPLATE Prepared By fzz d2 1viewed By EnJ eils' F4CaC- m u9--2W
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Page 193 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 TA 2005-15 APPENDIX D SKETCH 04 PAGE 8 OF 8 MAIN STEAM LINE 'D' LOWER STRAIN GAGE LCICAT1ON AND 'TU TEMPLATE Prepared By 4Zt/, -Reviewed By ,
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Page 194 of 198
Temporary Alteration 2005-15 Installation of Strain Gages on the Main Steam Line Piping in the Drywell REV-01 I
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v t e Letter Sequence Other
TAC:MC0761, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 30 December 2003 19 March 2004 28 May 2004 6 July 2004 1 September 2004 21 December 2004 28 March 2005 14 April 2005 27 July 2005 7 September 2005 28 October 2005 25 November 2005 Answers 1 April 2005 Results Approval, Approval, Approval Other: BVY 06-014, E-mail, Meyer, Entergy, to Ennis, NRR, VY EPU, BVY 06-019, Vermont Yankee, Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and Fiv Effects, BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan, BVY 06-039, Vermont Yankee Nuclear Power Station Revision 2 to Steam Dryer Monitoring Plan, BVY 06-051, Vermont Yankee - Summary of Reactor Feedwater Pump Trip Analysis, BVY 06-056, Submittal of Vermont Yankee Report on the Results of Steam Dryer Monitoring, BVY 06-080, Vermont Yankee, Extended Power Uprate - License Amendment No. 229 Clarifications to Nrc'S Final Safety Evaluation, BVY 06-087, Update to Information Related to 10CFR50.63 Licensing Basis, ML033140025, ML033160187, ML040080573, ML040090411, ML041810022, ML041810433, ML042180463, ML042650265, ML042680087, ML043020494, ML050060086, ML050280310, ML050450423, ML050940230, ML050940242, ML052080154, ML053490030, ML053530148, ML060330490, ML060410119, ML061290566, ML061870277
MONTHYEAR2004-12-09 [Table View]

BVY 06-019, Vermont Yankee, Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and Fiv Effects

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8.0 Evaluation

3.0 Record

SUMMARY

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