ML092320116

Duane Arnold Energy Center - Request for Additional Information Regarding Your Nine Month Response to NRC Generic Letter 2009-01. Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (TAC No

ML092320116
Person / Time
Site:	Duane Arnold
Issue date:	08/28/2009
From:	Feintuch K D Plant Licensing Branch III
To:	Costanzo C Duane Arnold
Feintuch K D, NRR/DORL/LPL3-1, 415-3079
References
GL-08-001, TAC MD7824
Download: ML092320116 (4)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 28, 2009 Mr. Christopher Costanzo Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 DUANE ARNOLD ENERGY CENTER -REQUEST FOR ADDITIONAL INFORMATION REGARDING YOUR NINE MONTH RESPONSE TO NRC GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7824)

Dear Mr. Costanzo:

The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your response dated October 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No.

ML082970263), pertaining to the subject Generic Letter (GL). On August 13, 2009, the NRC staff transmitted a draft Request for Additional Information (RAI) and discussed the draft RAI with your staff in a conference call on August 19, 2009. Enclosed please find the final RAI dated August 19, 2009, which is identical in content to the draft RAI of August 13, 2009, except for the deletion of item 2 from the requested information. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAI.

Sincerely, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc Distribution via REQUEST FOR ADDITIONAL INFORMATION DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 Guidance on U.S.

Nuclear Regulatory Commission (NRC) staff expectations is provided by Reference 1 which is generally consistent with Nuclear Energy Institute (NEI) guidance provided to industry in Reference 2 as clarified in later NEI communications. The NRC staff recommends that the licensee consult Reference 1 when responding to the following requests for additional information: In page 4 of the submittal [Ref. 3], the licensee stated, "..... the DAEC licensing basis has no specific requirements regarding precluding gas accumulation (voiding) in piping systems (suction or discharge) for either the Containment Spray or Decay Heat Removal functions as a condition for Operability. This is principally because these are manually initiated systems, that are generally not vulnerable to water hammer concerns, and they have no specific timing requirements for initiation in response to any analyzed event in the DAEC UFSAR." The staff reiterates that the Generic Letter (GL) is intended for addressing all modes and all operating conditions, and it is not limited to events and accidents evaluated in the updated final safety analysis report. The staff believes that since the Containment Spray and Decay Heat Removal systems have been specifically identified as within the scope of the GL, it needs to be addressed. The staff, therefore, requests the licensee to clarify whether the Containment Spray or Decay Heat Removal systems are intended to be used for any other safety functions for any modes of operation, including shutdown mode; for example, to mitigate loss of shutdown cooling accidents. If needed, then justify whether the licensee would be able to or have sufficient time to vent the piping during such events. Deleted -information not required at this time. In page 9 of the submittal [Ref. 3], the licensee stated, "The review of plant drawings confirmed that piping high points either had vent valves at those locations or were capable of being dynamically vented during system operation (e.g., inverted piping loops would be flushed during system operation, such as during post-maintenance testing prior to return to service.)" Confirm whether the pump test flow rates are adequate to remove voids. If not, would the maximum flow rate achieved during actual events move potential remaining voids? Did Duane Arnold Energy Center (DAEC) consider the difference? Provide Froude numbers associated with the test and maximum flow rates. Describe the method used to determine void volume when it is discovered. With respect to discharge side piping in the subject systems, in page 15 of the submittal [Ref. 3], the licensee stated, "These procedures require venting at high point locations in the respective systems and ensure adequate pressure is available to perform the venting. They were determined to have no other acceptance criteria than to ensure that a steady stream of water is observed when venting. This is consistent with meeting the specific requirement of the SRs to verify that the piping system is filled with water." ENCLOSURE

-2Justify how the current requirement of piping system "filled with water" assures that the acceptance criteria of system operability is met; and ensures that all voids, including trapped voids, have sufficiently been vented. Until resolution of the technical specification (TS) issues related to GL 2008-01 is complete, identify supplementary actions, such as use of procedures and other processes, to address control of voids in the subject systems that are not covered by the current DAEC TS requirements. Training was not identified in the GL, but is considered to be a necessary part of applying procedures and other activities when addressing the issues identified in the GL. Training should be briefly discussed.

REFERENCES Ruland, William H., "Preliminary Assessment of Responses to Generic Letter 2008-01, 'Managing Gas Accumulation in emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,' and Future NRC Staff Review Plans," NRC letter to James H.

Riley, Nuclear Energy Institute, ML091390637, May 28,2009. Riley, James H., "Generic Letter (GL) 2008-01, 'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems' Evaluation and 3 Month Response Template," Letter to Administrative Points of Contact from Director, Engineering, Nuclear Generation Division, Nuclear Energy Institute, Enclosure 2, "Generic Letter 2008-01 Response Guidance," March 20, 2008. R.L. Anderson, "Nine-Month Response to NRC Generic Letter 2008-01 -Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," Vice President, Duane Arnold Energy Center, FPL Energy Duane Arnold, LLC, October 13, 2008.

August 28, 2009 Mr. Christopher Costanzo Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER -REQUEST FOR ADDITIONAL INFORMATION REGARDING YOUR NINE MONTH RESPONSE TO NRC GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7824)

Dear Mr. Costanzo:

The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your response dated October 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082970263), pertaining to the subject Generic Letter (GL). On August 13, 2009, the NRC staff transmitted a draft Request for Additional Information (RAI) and discussed the draft RAI with your staff in a conference call on August 19, 2009.

Enclosed please find the final RAI dated August 19, 2009, which is identical in content to the draft RAI of August 13, 2009, except for the deletion of item 2 from the requested information.

Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAJ. Sincerely, IRAJ Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

Request for Additional Information cc w/encls:

Distribution via t.lstserv' DISTRIBUTION:

PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDoriDpr Resource RidsRgn3MailCenter Resource ADAMS ACCESSION NUMBER*

ML092320116 OFFICE NRRlLPL3-1/PM NRRlLPL3-1/LA NRR/LPL3-1/BC NAME KFeintuch BTuily ffHarris for LJames DATE 08/26/09 08/20/09 08/28/09 OFFICIAL RECORD COpy