Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- 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, 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, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML070370281, ML073100027, ML073510180, ML080360067, ML080430700, ML080500171, ML080530256, ML081010450, ML081010451, ML081120502, ML081700294, ML081720078, ML081760295, ML082040065, ML082050462, ML082100425, ML082810470, ML083120308, ML083240224, ML083250083, ML090130718, ML090340528, ML090720951, ML090760630, ML091320366, ML092020345, ML092430520, ML092440518, ML092460495, ML092460496, ML092460497, ML092460498, ML092460500, ML092540483, ML092680057, ML12319A076, ML13044A498
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MONTHYEARML0631104352006-11-0707 November 2006 Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Project stage: Request 05000260/LER-2007-001, Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test2007-03-0202 March 2007 Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test Project stage: Request ML0711300782007-04-18018 April 2007 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Supplemental Response to Requests for Additional Information (RAI) Project stage: Supplement ML0711503662007-04-24024 April 2007 Units 1, 2, & 3 - Fire Protection Program - Post-Fire Operator Manual Actions Project stage: Request ML0711503712007-04-24024 April 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Evaluations Project stage: Request ML0712905652007-05-16016 May 2007 Withholding Information from Public Disclosure, Response to Nuclear Regulatory Commission (NRC) Request for Additional Information - Round 12 for Browns Ferry EPU: Supplemental to SBWB-64 Project stage: RAI ML0716303492007-06-15015 June 2007 Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2 and 3, Steam Dryer Review Project stage: Meeting ML0718700242007-07-0303 July 2007 Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 - Supplement 1 Project stage: Request ML0717801902007-07-0505 July 2007 Request for Additional Information for Extended Power Uprate - Round 13 (TS-431 and TS-418 Project stage: RAI ML0719004762007-07-10010 July 2007 Meeting with the Tennessee Valley Authority (TVA) Concerning the Pending ACRS Meeting on the Browns Ferry Extended Power Uprate Project stage: Meeting ML0721501562007-07-18018 July 2007 Slides from Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations Project stage: Request ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz Project stage: Request ML0721400442007-08-0808 August 2007 Summary of Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting 05000259/LER-2007-005, Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank2007-08-0808 August 2007 Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank Project stage: Request ML0723602572007-08-21021 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Limit Curves Project stage: Request ML0724805472007-08-31031 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure Project stage: Request ML0727606602007-10-0909 October 2007 Request for Additional Information for Extended Power Uprate - Round 14 (TS-418) Project stage: RAI ML0728902372007-10-18018 October 2007 Request for Withholding Information from Public Disclosure Concerning Round 13 Request for Additional Information for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263 and MD5264) Project stage: RAI ML0729603112007-10-22022 October 2007 Technical Specification (TS) Changes TS-431 & TS-418, Extended Power Uprate - EPU Large Transient Testing Project stage: Request ML0731000272007-11-0909 November 2007 Request for Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418-S) Project stage: Other ML0732303482007-11-15015 November 2007 Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure APLA-35/37 Project stage: Request ML0733304832007-11-21021 November 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Preliminary Findings on Steam Dryer Stress Analysis Project stage: Request 05000296/LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe2007-11-21021 November 2007 Leak in an ASME Class I Code Reactor Pressure Boundary Pipe Project stage: Request ML0735101802007-12-14014 December 2007 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Schedule Regarding Analysis for Steam Dryers Project stage: Other ML0734607572007-12-19019 December 2007 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac No. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0735400102008-01-25025 January 2008 Summary of Meeting with Tennessee Valley Authority on Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264), Browns Ferry Units 1, 2, and 3 Project stage: Meeting ML0801504182008-01-25025 January 2008 (Public Version) - Summary of December 10, 2007 Meeting with TVA on Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0803205212008-01-25025 January 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) Response to Round 15 Request for Additional Information (RAI) - APLA-38/40, SRXB-71, and SRXB-72 Project stage: Request ML0803600672008-01-25025 January 2008 Steam Dryer RAI 15 Status, Slides Project stage: Other ML0802501652008-01-30030 January 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263, and MD5264) Project stage: Withholding Request Acceptance ML0803805602008-01-31031 January 2008 Technical Specifications (TS) Change TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 Request for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Request ML0804307002008-02-11011 February 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Schedule Regarding EPU Project stage: Other ML0804304462008-02-11011 February 2008 Notification of Potential Part 21 Report Power Supply Unit Is Limited at Elevated Temperatures Project stage: Request ML0803503812008-02-14014 February 2008 Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review Project stage: Meeting ML0806501012008-02-21021 February 2008 Response to Round 16 Request for Additional Information SRXB-73 Project stage: Request ML0805302562008-02-21021 February 2008 Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments Project stage: Other ML0804506472008-02-27027 February 2008 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0803506982008-02-29029 February 2008 Request for Additional Information for Extended Power Uprate - Round 16 (TS-431 and TS-418) (TACs MD5262, MD5263, MD5264) Project stage: RAI ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 Project stage: Request ML0811205102008-03-20020 March 2008 Summary of March 20, 2008, Meeting with Tennessee Valley Authority Regarding Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264) - Slides Project stage: Meeting ML0810104502008-04-0404 April 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 and Round 16 Requests for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Other ML0810104512008-04-0404 April 2008 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan Project stage: Other ML0817602952008-04-0909 April 2008 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Confirmation of Commitment Completions Project stage: Other ML0811205022008-04-16016 April 2008 CDI Incoming Letter Dated April 16, 2008 Regarding NRC Presentation Entitled, Tennessee Valley Authority Browns Ferry Nuclear Plant - Extended Power Uprate Steam Dryers Project stage: Other ML0811302312008-04-17017 April 2008 Public Slides - Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review, Project stage: Meeting ML0811200332008-04-30030 April 2008 Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure for Round 15 Fuels Responses Project stage: Withholding Request Acceptance ML0812806272008-05-0101 May 2008 Technical Specifications Change TS-418, Extended Power Uprate Supplemental Response to Round 16 Request for Additional Information - SRXB-87 & SRXB-89 Project stage: Supplement ML0812804712008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 Project stage: RAI ML0805001712008-05-0202 May 2008 Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418) Project stage: Other 2007-07-05
[Table View] |
Text
ENCLOSURE 5 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2,
AND 3 TECHNICAL SPECIFICATIONS (TS)
CHANGES TS-431 AND TS-418 EXTENDED POWER UPRATE (EPU)
BFN STEAM DRYER MONITORING PLAN
STEAM DRYER MONITORING PLAN Introduction and Purpose The Browns Ferry Nuclear Plant (BFN)
Steam Dryer Monitoring Plan (SDMP) provides actions for monitoring of Units 1, 2 and 3 for evidence of flow induced vibration that could result in fatigue stress limits being exceeding for the steam dryers.
Steam dryer stress analyses have been performed based upon measurements of pressure pulsations in the main steam lines (MSL) at 3458 megawatt thermal (MWt) determined by arrays of eight strain gages mounted in two separate locations on each steam line for a total of eight arrays.
These pressure pulsations provide input to an Acoustic Circuit Model (ACM) which predicts cyclic pressure loads on the steam dryers.
The cyclic pressure loads provide input to a Finite Element Model (FEM) of the steam dryer which calculates maximum and alternating stresses that can be compared to ASME Code limits.
During power ascension above 3458 MWt, data from the same strain gage arrays are recorded and used to predict changes in steam dryer stress as the steam line signals change with increasing steam flow.
This is accomplished by comparing the frequency spectrum and amplitude of the strain gage signals at each of the eight array locations to established limit curves.
Scope The SDMP applies to BFN Units 1, 2 and 3 above 3458 MWt until testing is completed at 3952 MWt and final results are submitted to the NRC.
Long term steam dryer inspection is also performed to verify steam dryer performance at extended power uprate (EPU) conditions.
These inspections are governed by BWRVIP-139.
Portions of the SDMP are required to comply with license conditions associated with the EPU license amendment.
These license conditions are listed in Table 3.
Power Ascension Test Control EPU power ascension above 3458 MWt is performed in small controlled steps in conjunction with the EPU power ascension test plan (PATP).
E5-1
HOLD POINTS Hold points above 3458 MWt will be established at increments of approximately 2.5% of 3458 MWt for data collection and evaluation.
TEST PLATEAUS EPU test plateaus will be established at intervals of 5% of 3458 MWt according to the table below.
Thermal power will not be increased above the plateau until steam dryer test results are evaluated.
Each 5% plateau will be held for a minimum of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to allow for NRC review.
EPU Test Plateaus Relative to 100%
105%
110%
115%
3458 MWt Power (MWt) 3458 3631 3804 3952 Two levels of acceptance criteria are used for the SDMP.
LEVEL 1 Level 1 criteria indicate that limits could be exceeded.
If level 1 criteria are exceeded, reactor power is promptly reduced to a previously acceptable power level until an engineering evaluation concludes that further power ascension is justified.
LEVEL 2 Level 2 criteria indicate that limits are being approached.
If level 2 criteria are exceeded, power ascension is promptly suspended until an engineering evaluation concludes that further power ascension is justified.
Monitoring Parameters For the SDMP, the parameters to be monitored are shown in Table 1.
Stress Limit Curves Limit Curves (LC)
- Unit specific LCs are developed based on unit specific steam line data, dryer design and analyzed dryer stresses at 3458 MWt.
These curves utilize the resolved end to end bias and uncertainty determination developed from the qualification of the MSL strain gage, ACM, and FEM E5-2
methodologies.
During power ascension, MSL strain gage signals are filtered and converted to power spectral density (PSD) for comparison to limit curves.
Two levels of criteria are established.
Table 2 provides the actions to be taken if the LCs are exceeded.
LEVEL 1 The Level 1 criteria curves represent the 3458 MWt acoustic signature for each point in the frequency spectrum scaled by the most limiting alternating stress ratio from the stress analysis.
The Level 1 limit curves provide a conservative safeguard against the potential for dryer stresses becoming higher than allowable (13.6 ksi).
LEVEL 2 The Level 2 criteria curves represent 80% of the Level 1 limit curves (10.88 ksi).
These curves will be used for evaluation of plant data as collected at each test plateau.
Refer to CDI Technical Note No.
07-30, "Limit Curve Analysis with ACM Rev.
4 for Power Ascension at Browns Ferry Nuclear Unit 1," for a detailed discussion of the LC development.
NRC Notifications At each of the 5% power plateaus above 3458 MWt or if strain gage signals exceed the established Level 1 criteria, an evaluation of steam dryer performance from the SDMP will be provided to the NRC Project Manager via electronic transmission or fax.
TVA shall not increase reactor power above the power plateau for a minimum of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from the time of the NRC's receipt of this information.
This process will be repeated at each of the 5% power plateaus until EPU conditions are reached.
Results of the SDMP will be submitted to the NRC in a report within 60 days from completion of steam dryer power ascension testing.
NRC Approvals NRC approval is required prior to changes that result in the following key attributes being less restrictive:
" During initial power ascension testing above 3458 MWt, each test plateau increment shall be approximately 5 percent of 3458 MWt.
" Level 1 performance criteria; and E5-3
- The methodology for establishing the stress spectra used for the Level 1 and Level 2 performance criteria.
Long Term Actions
" BFN dryers will be inspected at each of the following two refueling outages following completion of the EPU power ascension.
" Inspections to be per General Electric Services Information Letter (SIL) 644, and/or BWRVIP-139, latest approved versions.
" Moisture carryover measurements will continue after power ascension based on SIL 644 recommendations.
- Equipment associated with temporarily installed pressure and vibration monitoring may be removed from service following achievement of one operating cycle.
E5-4
Table 1 - Steam Dryer Surveillance Requirements during Reactor Power Operation above a Previously Attained Power Level Parameter Surveillance Frequency Moisture Carryover Every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during power ascension (MC)
(Notes 1 and 2)
Main Steam Line At least once at every 2.5% above (MSL)Pressure data 3458 MWt from strain gages AND Within one hour after achieving every 2.5% above 3458 MWt(Note 3)
Main Steam Line data At least once at every 2.5% above from accelerometers 3458 MWt AND Within one hour after achieving every 2.5% above 3458 MWt(Note 3)
Reactor pressure, At least once at every 2.5% above water level, 3458 MWt individual steam line flow, and AND feedwater flow Within one hour after achieving every 2.5% above 3458 MWt(Note 3)
Notes:
- 1. MC to be in accordance with the recommendations of GE SIL 644, Sup 1, Rev. 1. Provided that the performance criteria are not exceeded, when steady state operation at any given power level exceeds 168 consecutive hours, MC monitoring frequency may be reduced to once a week.
- 2.
If MC cannot be determined within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of achieving a 5% power plateau, an orderly power reduction shall be made within the subsequent 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to a power level at which MC was previously determined to be acceptable.
- 3.
MSL pressure data shall be measured hourly when increasing power above a level at which data was previously attained.
Data is required once at each 2.5% power step above 3458 MWt.
If the surveillance is met at a given power E5-5
level, additional surveillances do not need to be performed at that power level where data had been previously obtained.
E5-6
Table 2 -
Steam Dryer Performance Criteria and Required Actions Performance Criteria Required Actions if Performance Criteria Exceeded and Required Completion Level 2:
" Moisture Carryover (MC)>0.1%
OR
" MC > 0.1% and increases by
> 50% over the average of the three previous measurements taken above 3458 MWt OR
" Pressure data >
Level 2 Spectra (Note 1)
- 1. Promptly suspend reactor power ascension until an engineering evaluation concludes that further power ascension is justified.
- 2.
Before resuming reactor power ascension, the steam dryer performance data shall be reviewed as apart of an engineering evaluation to assess whether further power ascension can be made without exceeding the Level 1 criteria.
Level 1:
OR
- Pressure data exceed Level 1 Spectra
- 1. Promptly initiate a reactor power reduction and achieve a previously acceptable power level within two hours, unless an engineering evaluation concludes that continued power operation at the current power level or power ascension is acceptable.
- 2.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, re-measure MC and perform an engineering evaluation of steam dryer structural integrity.
If the evaluation does not support continued plant operation, the reactor shall be placed in a hot shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the evaluation supports continued operation, implement step 3.
- 3.
If the engineering evaluation supports continued operation, reduce further power ascension step increases and plateau levels to nominal increases of 1.25% and 2.5% of 3458 MWt, respectively, for any additional power ascension.
E5-7
Notes:
- 1. The steam dryer limit curve spectra and dryer stress to MSL frequency correlations shall be determined and documented in an engineering calculation or report.
Acceptable Level 2 shall be based on maintaining <10.88 ksi.
Acceptable Level 1 Spectra shall be based on maintaining <13.6 ksi.
The Level 1 and Level 2 LCs and stress limits shall be adjusted for uncertainty.
E5-8
Table 3 -
Steam Dryer License Conditions Requirement
<This table will contain the final approved steam dryer license conditions.>
E5-9