Letter Sequence Response to RAI |
|---|
|
|
MONTHYEARML0926104352009-09-11011 September 2009
R. E. Ginna - Fifth Ten-Year Inservice Test Program for Safety-Related Pumps and Valves
Project stage: Request
ML0927505172009-10-0101 October 2009
E-mail Ginna Acceptance Review of IST Relief Requests
Project stage: Acceptance Review
ML0929504852009-10-16016 October 2009
Response to Request for Additional Information Associated with Inservice Test Program Relief Request Number PR-01
Project stage: Response to RAI
ML0931400912009-11-0505 November 2009
R. E. Ginna Nuclear Power Plant, Withdrawal of Relief Request VR-03 from the Fifth Ten-Year Inservice Test Program for Safety-Related Pumps and Valves
Project stage: Withdrawal
ML0935701732009-12-30030 December 2009
Alternative Requests for Fifth 10-Year Pump and Valve Inservice Testing Program-R.E. Ginna Nuclear Power Plant
Project stage: Acceptance Review
ML1000601112010-01-19019 January 2010
Correction Letter to Alternative Requests for Fifth 10-Year Pump and Valve Inservice Testing Program-R. E. Ginna
Project stage: Other
ML1006903082010-03-0202 March 2010
R. E. Ginna Nuclear Power Plant - Commitment Associated with Technical Specification LCO 3.4.14 RCS Pressure Isolation Valve (PIV) Leakeage
Project stage: Request
ML1008902372010-04-14014 April 2010
Alternative Request GR-01 for the Fifth 10-Year Pump and Valve Inservice Testing Program-R.E. Ginna Nuclear Power Plant
Project stage: Other
2009-12-30
[Table View] |
Similar Documents at Ginna |
|---|
Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024
LLC - Integrated Inspection Report 05000244/2023004
ML24026A0112024-01-26026 January 2024
R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump
IR 05000244/20230102023-12-19019 December 2023
LLC - Age-Related Degradation Inspection Report 05000244/2023010
ML23348A0992023-12-15015 December 2023
R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23347A0092023-12-13013 December 2023
Annual Commitment Change Notification
ML23346A0142023-12-12012 December 2023
LLC - Senior Reactor and Reactor Operator Initial License Examinations
ML23341A1252023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
ML23321A1392023-11-17017 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000244/20230032023-10-25025 October 2023
LLC - Integrated Inspection Report 05000244/2023003
ML23292A0282023-10-19019 October 2023
LLC - Notification of Conduct of a Fire Protection Team Inspection
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
ML23258A1382023-09-18018 September 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010
IR 05000244/20230052023-08-31031 August 2023
Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005)
ML23158A1952023-08-30030 August 2023
R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications
ML23235A1722023-08-23023 August 2023
Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
IR 05000244/20234012023-08-15015 August 2023
LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only)
IR 05000244/20230022023-08-0303 August 2023
LLC - Integrated Inspection Report 05000244/2023002
ML23191A0592023-07-21021 July 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
IR 05000244/20234022023-07-19019 July 2023
R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only)
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
ML23135A0412023-05-15015 May 2023
2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report
ML23121A0482023-05-0101 May 2023
R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
IR 05000244/20230012023-04-26026 April 2023
LLC - Integrated Inspection Report 05000244/2023001
ML23100A0302023-04-10010 April 2023
2023 10 CFR 50.46 Annual Report
ML23114A1152023-03-29029 March 2023
Electronic Reporting of Exposure Data for 2022
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23075A0872023-03-15015 March 2023
R. E. Ginna Nuclear Power Plant - Project Manager Assignment
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000244/20220062023-03-0101 March 2023
Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006)
ML22364A0242023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
ML23060A1622023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
ML23005A1762023-02-23023 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes
ML23005A1222023-02-22022 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023
Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
ML22287A0692023-02-0808 February 2023
R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
ML23031A2992023-02-0707 February 2023
R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request
ML23010A0112023-02-0101 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
IR 05000244/20223012023-01-20020 January 2023
Initial Operator Licensing Examination Report 05000244/2022301
IR 05000244/20220122023-01-12012 January 2023
LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012
ML22362A0382022-12-28028 December 2022
R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML22348A2062022-12-14014 December 2022
Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
2024-02-05
[Table view] |
Text
Paul Swift Swift R.E.
R.E. Ginna Ginna Nuclear Nuclear Power Power Plant, Plant, LLC LLC Manager, Manager, Nuclear Nuclear Engineering Engineering Services Services 1503 1503 Lake Road Road Ontario, New York Ontario, New York 14519-9364 14519-9364 585.771.5208 585.771.5208 585.771.3392 585.771.3392 Fax Fax Paul.swift@constellation.com Paul.swift@constellation.com 0 <"'\*
Constellation Energy" Nuclear Generation Nuclear Constellation Generation Group Group Energy*
October October 16, 2009 2009 U. S. Nuclear Nuclear Regulatory Regulatory Commission Washington, Washington, DC 20555 20555 ATTENTION:
ATTENTION: Document Control Document Control Desk
SUBJECT:
R.E. Ginna Nuclear N ucIear Power Plant Plant Docket No. 50-244 50-244
Response
Response to Request Request for Additional Information Associated Information Associated With With Inservice Inservice Test Program Program Relief Request Number ReJiefRequest Number PR-01PR-Ol
References:
(1) Letter Letter from P. Swift, Ginna Ginna LLC, to NRC Document Document Control Desk,
Subject:
Subject:
Fifth Ten-Year Ten-Year Inservice Inservice Test Test Program Program for Safety-Related Safety-Related Pumps and Valves, Valves, dated dated September 11,2009.
11, 2009.
(2)
(2) Letter from D. Pickett, NRC, to J. Carlin, Ginna LLC,
Subject:
Request for Additional Information (RAI) Re: Relief Request No. PR-Ol, Additional PR-01, Revision 0, for the Fifth 10-Year Inservice Inservice Testing Interval - R.E. Ginna Nuclear Power Plant (TAC Testing Interval-NO. ME2239), dated October October 6, 2009.
On September 11,200911, 2009 R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) submitted relief request PR-01 associated with the Fifth Ten-Year Inservice Test Program for Safety-Related Safety-Related Pumps and Valves (Reference 1). On OctoberOctober 6, 2009 the NRC responded to that submittal with a request for additional information (Reference (Reference 2). Enclosed please find the response to the staffs staff's question.
commitments contained in this letter. Should you have questions regarding this There are no regulatory commitments matter, please contact Thomas Harding (585) (585) 771-5219, or thomas.hardingjr@constellation.com.
thomnas.hardingjrgconstellation.com.
Very truly yours, Swift Paul M. Swift
Attachment:
Response to Request for' for Additional Information Associated With Relief Relief Request Number PR-Ol PR-01 AJ4L7 (74 1.J'0 L'Ni q 6 - /00ý?0'03
Document Control Desk October 16, 2009 October Page 2 cc: S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC
ATTACHMENT ATTACHMENT Response to Request for Additional Information Response Associated With Information Associated Request Number PR-Ol Relief Request PR-01 RE. Ginna Nuclear Power Plant, LLC R.E.
16, 2009 October 16,
ATTACHMENT ATTACHMENT
Response
Response to RequestRequest for Additional Information Associated Associated With Relief Request Number PR-Ol PR-01 Question Question It is the NRC staff's understanding understandingthat the diesel transferpumps PDG02A diesel fuel oil transfer PDGO2A and and PDGO2B PDG028 are positive displacement are displacement pumps. Please Please explain explain how the proposedproposedalternative alternative testing methodology utilizingutilizing the accuracy accuracy in design design analysis 4526-ME-20 meets the analysis EWR 4526-ME-20 recommendations recommendations as described described in NUREG-1482, NUREG-1482, Revision 1, Section 5.5.2.
1, Section 5.5.2.
Response
Ginna's Ginna's diesel fuel oil transfer pumps, PDG02A & & PDG02B, are positive displacement displacement pumps.
The flow rate for these pumps is determined determined by measuring measuring the indicated level change change in in the the diesel generator generator fuel oil day tank during a timed pump run and converting this data into fuel oil transfer pump flow rate for both the Group 8B and comprehensive comprehensive pump tests.
Level Gauges LG-2044 ("A" E DIG) and LG-2045 LG-2045 ("8" ("B" EE DIG) are utilized to measure the the change change in in indicated level while the fuel oil transfer pump is running and restoring fuel oil day tank level. 80th Both LG-2044 LG-2044 and LG-2045 (sight glasses equipped equipped with a reference scale in in inches of level) inches level) have a range of indicatedindicated level of 99 inches (2.5 inches to 11.5 11.5 inches).
The respective day tank is drained drained to an initial indicated indicated level of 5.0 to 5.5 inches before before initiating the fuel oil pump start. This level level is logged as the initial level. The pump is then started coincident coincident with with starting starting the stopwatch and the system allowed allowed to stabilize. A minimum 2 minute minute stabilization stabilization period is observed for the comprehensive comprehensive test.
Following a total minimum run time of 5 minutes (or exceeding Following exceeding an indicated tank level of 11 11 inches),
inches), the pump is stopped coincident coincident with stopping the stopwatch the. stopwatth and the day tank level is read in in inches to the nearestnearest 0.25 inch. This level is logged as the final level.
The change in in day tank level is determined determined in in inches and then converted converted to total gallons gallons pumped using the constant conversion conversion factor of 24.76 gallons per inch. The constant of 24.76 gallons per gallons per inch inch ofof indicated indicated level level on on the day day tank tank sight sight glass was established by EWR 4526-ME-20 based on the tank's geometrical ME-20 based on the tank's geometrical dimensions. dimensions.
i The total The total gallons gallons pumped pumped is is then then divided by the total total pump pump runrun time time to to arrive at the arrive at the pump pump test flow rate rate inin gallons gallons per minuteminute (gpm). This calculation calculation is documented documented in in the pump test procedures.
procedures.
The test circuit The test circuit for for each each pump is a fixed flow path from the storage tank (pump suction) to the the day tank (pump discharge).
day tank (pump discharge). Pump Pump suction suction pressure pressure is nearly constant because of the very small change in in storage tank level. This change change in in suction pressure during pump operation is is considered negligible.
considered negligible. The The normal normal rise rise in day tank level in day level is is approximately approximately 5.5 inches, which which corresponds to corresponds to aa quantity quantity of of approximately approximately 136 gallons pumped 136 gallons pumped during the the 55 minutes of pump pump operation, resulting in operation, in a typical typical flow rate rate of approximately approximately 27 gpm. The current flow rate rate reference values of each reference each pump pump are as follows: PDG02A - 27.2 gpm, PDG028 PDG02B - 27.1 gpm.
1I
ATTACHMENT ATTACHMENT Response to Request for Additional Information Associated Additional Information Associated With Relief Request Number PR-Ol PR-01 The small rise inin day tank level during pump operation does not affect pump discharge discharge pressure pressure or flow rate. This conclusion is supported supported by the discussion discussion inin NUREG 1482 Rev.1, section Rev.1, section 5.5.2, where the NRC states: "Pump discharge discharge pressure will match match system pressure up to the the shutoff head head of the positive displacement Because of the characteristics displacement pump. Because characteristics of a positive positive displacement pump, there should be virtually no change in displacement in pump discharge discharge flow rate as a result of the rising tank level.
of level. Therefore, Therefore, rising tank level will not have an impact on test results. By By having approximately approximately the same level in in the tank at the beginning beginning of each test, licensees licensees can achieve repeatable results."
The accuracy of level gauges, LG-2044 and LG-2045, is determined The accuracy determined using the nine (9) inch indicated range of level and the constant of 24.76 gallons per inch. This yields a total volume indicated volume change of 222.84 gallons. Based change Based on a readability uncertainty of +/- 0.125 inch (0.25 inch readability uncertainty scaling),
scaling), which isis equivalent equivalent to 3.10 gallons, divided by the total indicated volume of 222.84222.84 gallons, the overall accuracy accuracy of the sight glass is +/- 1.39%.
In addition, the stopwatch In stopwatch used to measure measure the time the pump is operating and pumping pumpirig fuel oil accurate to within +/-+/- 0.6 seconds per minute for a calibrated accuracy is accurate accuracy of +/- 1.0%. Combining
+/- 1.0%. Combining the accuracies accuracies ofof the the level level gauge sight glass and stopwatch, using the square square root of the sum of the squares method, results in in an overall indicated indicated accuracy accuracy of +/- 1.711.71%. overall accuracy
%. This overall unchanged from that which relief was granted is unchanged granted for during th 10-year during the 44th interval 1ST 10-year interval IST program.
2
