ML060810218: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[L-97-004, Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls]]
| number = ML060810218
| issue date = 03/03/2006
| title = R.E. Ginna Nuclear Power Plant, Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls
| author name = Korsnick M G
| author affiliation = Constellation Energy Group, R. E. Ginna Nuclear Power Plant, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000244
| license number = DPR-018
| contact person =
| case reference number = GL-97-004
| document type = Letter
| page count = 5
}}
 
=Text=
{{#Wiki_filter:Maria Korsnick Site Vice President Constellation Energy, Generation Group R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick@constellation.com March 3, 2006 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 Response to Requests for Additional Information Regarding Topics Discussed on Conference Calls By letter dated July 7, 2005, as supplemented by letters dated August 15 and September 30, 2005, R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) submitted an application requesting authorization to increase the maximum steady-state thermal power level at the R.E. Ginna Nuclear Power Plant from 1520 megawatts thermal (MWt) to 1775 MWt.The purpose of this letter is to provide formal documentation of any outstanding requests received to date as well as our response.
Our responses are contained in Attachments 1 and 2.Attachment 1 contains the question and answer from a February 7, 2006 question regarding ECCS NPSH.Attachment 2 contains the question and answer from a February 7, 2006 question regarding Operator Response to Feed Line Break in Intermediate Building.The responses do not include any new regulatory commitments.
If you have any questions, please contact George Wrobel at (585) 771-3535 or george.wrobel~constellation.com.
Very truly yours, Mary Korsnick 1oDl I 0(0 J 9 STATE OF NEW YORK COUNTY OF WAYNE TO WIT: 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.JI lg Subscribed and sworn before me, a Notary Public in and for the State of New York and County of -ln 2o , this .. .:dayof l2( J , 2006.WITNESS my Hand and Notarial Seal: My Commission Expires: com A1h6&L &MA Notary Public: -SHARON L MILLER Notay Pubc State of New York Rasirb No. 01MI6017755 misski Domre DrA 21,200 v(
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 QUESTION AND ANSWER FROM FEBRUARY 7,2006 REGARDING ECCS NPSH NRC Question #1: Is the licensing basis for EPU ECCS and containment spray pump NPSH calculations still contained in the Ginna response to GL 97-04 (Letter to NRC dated January 6, 1998)?Ginna Response: The licensing basis for the Ginna EPU ECCS and containment spray pump NPSH calculations has been updated since the Ginna response to GL 97-04 (Letter to NRC dated January 6, 1998). Ginna has implemented a change in the manner in which the RHR discharge throttle valves are operated in the ECCS system. The valves are permanently throttled to avoid the need for operator action to position the valves post-LOCA.
A revised analysis has been completed to support this new throttle position.
This change has been made to address an identified concern related to reducing operator dose post-LOCA.
The UFSAR will be updated to reference the new analysis.These activities are not affected by EPU. The analyses for EPU assumed a reduced level of ECCS flow, which provided adequate core cooling during the injection phase while reducing the required NPSH during the recirculation phase, as compared to the pre-EPU analysis.
ATTACHMENT 2 QUESTION AND ANSWER FROM FEBRUARY 7,2006 REGARDING OPERATOR RESPONSE TO FEED LINE BREAK IN INTERMEDIATE BUILDING NTRC Question #1: In their submittal, section 2.8.5.2.4. (Feedwater system pipe breaks inside and outside containment), the licensee presumes that AFW is started at time 891.8 seconds into their most limiting event.Specifically, table 2.8.5.2.4-1 mentions this. Since their analysis starts the event at 20 seconds and the protection system trips the reactor 1.8 seconds after that, this means the operators have 870 seconds to restore the required AFW flow.Is it reasonable to presume the operators can restore the required AFW flow within 870 seconds?Ginna Response Ginna will assure that Standby Auxiliary Feed Water (SAFW) flow is delivered within 870 seconds as required by the Feed Line Break safety analysis by optimizing the emergency procedures, training on the procedures and verifying the procedures using the simulator prior to implementing the EPU. The emergency procedures will be optimized by relocating certain verification steps in E-0 to an attachment where they can be performed independently.
The SAFW flow initiation step in FR-H.1 will also be relocated to an earlier step which will further reduce the time to SAFW flow initiation.
These emergency procedures will be verified using operating crews on the plant simulator.
As part of this simulator training the time line will be verified to meet safety analysis assumptions.
These results will be documented prior to startup from the 2006 refueling outage and escalation to the uprated power level.}}

Latest revision as of 20:51, 23 November 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML060810218&oldid=2194432"