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TAC:MC7382, Steam Generator Tube Integrity (Approved, Closed) |
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MONTHYEARML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate Project stage: Request ML0523101552005-08-15015 August 2005 Supplemental Information Related to Small Break (SB) Loss of Coolant Accident (LOCA) Analysis and Post-LOCA Boric Acid Precipitation Analysis Project stage: Request ML0524500902005-09-0202 September 2005 Forthcoming Meeting with R.E. Ginna Nuclear Power Plant, LLC (Ginna, Llc), Regarding Extended Power Uprate Amendment Application Project stage: Meeting ML0524504522005-09-15015 September 2005 Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing - Extended Power Uprate - R.E. Ginna Nuclear Power Plant Project stage: Other ML0529208222005-09-15015 September 2005 Presentation for 09/15/2005 Meeting with R. E. Ginna SBLOCA EPU Results Summary Project stage: Meeting ML0525502722005-09-30030 September 2005 Westinghouse Electric Company, Request for Withholding Information from Public Disclosure for R. E. Ginna Nuclear Power Plant Project stage: Withholding Request Acceptance ML0528002232005-09-30030 September 2005 R. E. Ginna, Large Transient Tests Associated with License Amendment Request Regarding Extended Power Uprate Project stage: Request ML0529205102005-10-24024 October 2005 Summary of Meeting with R.E. Ginna Extended Power Uprate Application Project stage: Meeting ML0530705682005-11-0303 November 2005 Forthcoming Meeting with R.E. 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Ginna Nuclear Power Plant, LLC, Regarding Extended Power Uprate Amendment Application Project stage: Meeting ML0534803882005-12-0606 December 2005 Response to Requests for Additional Information Regarding Topics Described by Letter Dated October 25. 2005 Project stage: Response to RAI ML0536101852005-12-19019 December 2005 Response to Requests for Additional Information Re Increase of Maximum Steady-State Thermal Power Level Project stage: Response to RAI ML0536400802005-12-22022 December 2005 Response to Request for Additional Information Regarding Topics Described by Letter Dated November 10, 2005 Project stage: Response to RAI ML0535602452005-12-23023 December 2005 Summary of November 17, 2005, Meeting with R. E. Ginna Nuclear Power Plant, LLC, Regarding Extended Power Uprate Application Project stage: Meeting ML0601802622006-01-11011 January 2006 Supplemental Response to Requests for Additional Information Regarding Topics Described by Letters Dated August 24, 2005 and October 28, 2005 Project stage: Supplement ML0609604162006-01-25025 January 2006 R. E. Ginna - Response to Requests for Additional Information Regarding Topics Described in Meeting Minutes Project stage: Response to RAI ML0605403492006-02-16016 February 2006 Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls Project stage: Response to RAI ML0606806582006-03-0909 March 2006 Forthcoming Meeting with R. E. Ginna Nuclear Power Plant, LLC (Ginna Llc), Regarding Extended Power Uprate Amendment Application Project stage: Meeting ML0607901132006-03-20020 March 2006 Cancellation - Forthcoming Meeting with R.E. Ginna Nuclear Power Plant, LLC Regarding Extended Power Uprate Amendment Application Project stage: Meeting ML0609403122006-03-24024 March 2006 R. E. Ginna - Response to BOP Systems Questions Discussed on March 2, 2006 Conference Call Project stage: Request ML0609300252006-04-0404 April 2006 Notice of Meeting with R. E. Ginna Nuclear Power Plant, LLC (Ginna Llc), Regarding Extended Power Uprated Amendment Application Project stage: Meeting ML0608003152006-04-0606 April 2006 R. E. Ginna Nuclear Power Plant - Draft Environmental Assessment and Finding of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Draft Other ML0608003472006-04-0606 April 2006 R. E. Ginna Nuclear Power Plant Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Increase to Maximum Reactor Power Level Project stage: Draft Other ML0613503752006-05-0909 May 2006 R. E. Ginna, Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls for Extended Power Uprate (EPU) Project stage: Response to RAI ML0613706272006-05-12012 May 2006 Comment (1) of Kimberly A. Merchant on Draft Environmental Assessment and Findings of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Draft Other ML0614503812006-05-19019 May 2006 R. E. Ginna Final Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls for Extended Power Uprate (EPU) Project stage: Response to RAI ML0613204402006-06-26026 June 2006 R. E. Ginna Nuclear Power Plant - Final Environmental Assessment and Finding of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Other ML0616002502006-06-26026 June 2006 Final Environmental Assessment and Finding of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Acceptance Review ML0619205922006-07-11011 July 2006 Amendment 97, Renewed Facility Operating License Page No. 3 Regarding 16.8 Percent Power Uprate Project stage: Other ML0619205942006-07-11011 July 2006 R. E. Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate Project stage: Other ML0613801032006-07-11011 July 2006 R. E. Ginna, License Amendment, 16.8 Percent Power Uprate Project stage: Other ML0613802492006-07-11011 July 2006 Table of Contents, Safety Evaluation Related to Extended Power Uprate at R. E. Ginna Nuclear Power Plant Project stage: Approval ML0629101322006-10-12012 October 2006 License Amendment Request: Spent Fuel Pool Storage Capacity Project stage: Request 2006-01-11
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Maria Korsnick R.E. Ginna Nuclear Power Plant, LLC Site Vice President 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax Constellation Energy maria.korsnick@consteltation.com Generation Group September 30, 2005 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
R.E. Ginna Nuclear Power Plant Docket No. 50-244 Large Transient Tests Associated with License Amendment Request Regarding Extended Power Uprate
REFERENCES:
(a) Letter from Mary G. Korsnick, Ginna LLC, to NRC Document Control Desk,
Subject:
License Amendment Request Regarding Extended Power Uprate, dated July 7, 2005 In our 2005 Extended Power Uprate License Amendment Request (Reference (a)), R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) stated that a final proposal for large transient testing was still being developed and would be provided by September 30, 2005. This submittal provides the results of our evaluation of the benefits and risks associated with performing large transient tests as part of the EPU power escalation.
The proposed tests are described in Table I of the Attachment. These tests are comparable to the spectrum of tests normally associated with EPU escalation, with one addition - a manual turbine trip from approximately 30 per cent power level. As noted in the Attachment, we consider that this test is not required to demonstrate proper operation of control systems and verification of new setpoints (i.e., a large transient test is not required to demonstrate acceptability of the EPU). However, during the Operations review of our startup test plans, it was determined that this more integrated verification of control systems and setpoints would provide measurable benefits: exercise of control systems, verification of analytical models, response data for simulator tuning, and operator experience.
This test will now be factored into our startup test schedule from the 2006 refueling outage. If you have any questions, please contact George Wrobel at (585) 771-3535 or george.wrobelconstellation.com.
Very truly yo Mary G. Korsnick 4 0/
100 I (
STATE OF NEW YORK :
- TO WIT:
COUNTY OF WAYNE 1,Mary G. Korsnick, being duly sworn, state that I am Vice President- R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), and that I am duly authorized to execute and file this response on behalf of Ginna LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Ginna LLC employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
- '- 1gyb )°Y4'kt Subscribed and sworn before me, a Notary Public in and for the State of New York and County of 1Of7M e , this 5 day of Se4ffMM -,L2005.
WITNESS my Hand and Notarial Seal: ,'h SlwKk9O _,
Notary Public My Commission Expires:
SHMON L MILLER Noey Pb Stte of New York Re4st*aon No. O1Mh607755 Comr~W Dozaw2t, 2_
Attachments:
Cc: S. J. Collins, NRC P. D. Milano, NRC Resident Inspector, NRC Mr. Peter R. Smith New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy NYS Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223-1350
Attachment 1 Manual Turbine Trip Test for the Ginna EPU Summary Ginna LLC has evaluated the potential benefits and risks associated with additional large plant transient tests for the Ginna EPU and has concluded that a spectrum of tests should be performed. One of these tests, a manual turbine trip test at approximately 30% EPU power that will be performed as part of the power escalation test plan, is of greater scope than the tests normally conducted for an EPU. We have reviewed industry operating experience for pressurized water reactors that have undergone uprates and have not identified an event where the large plant transient response was unexpected or control system settings were set incorrectly, even absent this test. In addition, the proposed EPU is consistent with that already allowed for a plant similar in design to Ginna Station. This provides confidence in our analytical ability to correctly predict plant transient response and calculate appropriate control system settings and leads us to conclude that additional large plant transient tests are not required.'
However, Ginna LLC understands that our 17% EPU will be the largest one-time power uprate to date for a pressurized water reactor even though the final power level is consistent with that currently allowed for a plant similar in design to Ginna Station. After Operations review of the power escalation test plan, we have concluded that performing this type of manual turbine trip test is appropriate. A complete listing of the large plant transient tests in the power escalation test plan is provided as Table 1 to this attachment.
Purpose of Test The purpose of the manual turbine trip test will be to verify the dynamic large plant transient response and control system settings. The test will exercise control systems such as rod control, steam dump control, pressurizer level and pressure control, and steam generator water level control. The manner in which the control systems respond to the power and temperature mismatch as a result of the turbine trip will be verified, including the ability of the control systems'to achieve stable plant conditions in an acceptable range. In this manner the manual turbine trip test will fulfill the purpose of the pressurizer level control test (Startup Test #SU 4.2.3), pressurizer pressure control test (SU 4.1.3), and steam dump test (SU 4.9.2) performed during original plant startup testing for Ginna. The test will also provide large plant transient response data that will be used when necessary and appropriate to tune both the simulator and engineering design models. Finally, the test will provide an opportunity to gain operator experience with a load rejection transient under controlled conditions that may then be used to adjust operating procedures when necessary and appropriate.
Test Power Level The manual turbine trip test will be performed at approximately 30% EPU power. This power provides a stable condition from which to initiate the test shortly after the main turbine is paralleled to the grid. A turbine trip from this power level will cause a power mismatch resulting in a change to average coolant temperature, which will cause control systems to be exercised. An evaluation of the plant and control system response will be conducted and the results extrapolated to verify that plant response to transients from
Attachment 1 higher initial power levels will be acceptable. A manual turbine trip from approximately 30% EPU power will not present an unnecessary risk to creating an undesirable plant transient. Key plant parameters are predicted to maintain adequate margin to automatic protection features. Margins to protective features would be less for a test from higher power levels. Given the above, Ginna LLC has determined that a manual turbine trip test from approximately 30% EPU power appropriately balances the objectives of a load rejection test and overall plant risk.
Test Acceptance Criteria The acceptance criteria for the test will include verification that no reactor trip occurs and that pressurizer safety valves, main steam safety valves and pressurizer power operated relief valves do not open. The acceptance criteria will also include a requirement that the plant dynamic response is stable and converging on a range that supports safe operation at low power. Finally, if a plant transient occurs prior to performance of this test (e.g., manual turbine trip due to other reasons), which successfully demonstrates these objectives, then the proposed 30% EPU test will not be conducted.
Risk Mitigation Detailed planning and procedure preparation will precede the test to assure the increase in overall plant risk is mitigated. In particular, procedural criteria will be established to initiate operator manual control if malfunction of equipment is apparent.
Calibration checks and post-modification testing of control systems will be conducted prior to the test. Contingency plans will be developed and incorporated into the test procedure to respond to equipment malfunctions. Finally, if the transmission operator requests that this test not be performed (e.g., system demands), or risk management analysis consistent with 10 CFR 50.65 (a)(4) show that the risk of the test to be significant (e.g., severe weather), then the test will not be performed. In this way Ginna LLC intends to minimize the impact on overall plant risk caused by the test.
Attachment 1 Table 1 Large Plant Transient Tests in Ginna EPU Power Ascension Test Plan Proposed Test Description Expectation Turbine The turbine will be taken to This test will verify proper Overspeed Trip approximately 30% power, operation of the overspeed from 20% EPU ramped back to no-load, mechanism for the new HP Power with the reactor at turbine, proper operation of the approximately 20% power, new turbine control valves and and automatically tripped as exercise the steam dump system.
speed exceeds the mechanical overspeed trip setpoint unloaded.
10% Load Fast power ramps limited by These ramps will test NSSS and Change at new station license conditions BOP control system operation, to 30% and 100% and fuel pre-conditioning ensure that no unanticipated EPU Power considerations. aggregate effects have been produced by interaction of the plant modifications.
Manual Turbine The turbine will be manually Validate the control system Trip from 30% tripped causing a power setpoints, provide operator EPU Power mismatch and response of experience with a load rejection rod control, steam dump transient, and provide data to tune control, pressurizer level simulator and Westinghouse and pressure control and design analyses which predict steam generator level transient response for turbine trips control systems. from higher power levels.
Turbine Stop Standard turbine valve Validate dynamic performance of Valve, Governor testing augmented by post- new governor valve design to Valve, and modification tests ensure adequate transient Intercept Valve associated with HP Turbine response. Verify acceptable Testing at 50% and Governor Valve dynamic performance of the new EPU Power Replacement. HP turbine rotor during changes in individual arc steam flows.
Steam Generator Manually inserted level Verify SG level control system Level / setpoint step-changes in the response and acceptability of over-Feedwater Flow steam generator. Both up- shoot, damping and steady-state Dynamic testing going and down-going limit cycling at the new licensed at 30% and setpoint changes of different power level. Verify acceptable 100% EPU magnitudes will be inserted. operation of the digital feedwater Power control system.