ML20154L165

Submits RAI Re Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions

ML20154L165
Person / Time
Site:	Prairie Island
Issue date:	10/14/1998
From:	Kim T NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
GL-96-06, GL-96-6, TAC-M96854, TAC-M96855, NUDOCS 9810190164
Download: ML20154L165 (3)

Text

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u. p m\,} UNITED STATES a t s* NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. soses.cooi 878 M i

• $, October 14, 1998 l Mr. Roger O. Anderson, Director j

Nuclear Energy Engineering Northen States Power Company 414 Nicollet Mall Minneapolis, MN 55401  !

SUBJECT:

PRA!RIE ISLAND UNITS 1 AND 2 - REQUEST FOR ADDITIONAL  !

INFORMATION CONCERNING NORTHERN STATES POWER COMPANY'S  !

RESPONSE TO GENERIC LETTER (GL) 96-06, " ASSURANCE OF l EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING i DESIGN-BASIS ACCIDENT CONDITIONS"(TAC NOS. M96854/M96855) l

Dear Mr. Anderson:

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By letters dated October 30,1996 and January 28,1997, Northern States Power Company (NSP) submitted its 30-day and 120-day responses to GL 96-06. These submittals addressed the issues of waterhammer, two-phase flow, and thermally induced pressurization of piping runs i penetrating the containment. By a letter dated August 14,1997, the staff issued a request for additional information (RAI), and NSP responded to this RAI by a letter dated September 15, ,

1997. By a letter dated April 10,1998, the staff issued a follow-up RAI regarding the i "waterhammer" and the "two-phase flow" concerns based on its review of the NSP's I September 15,1997, submittal. On April 29,1998, a telephone conference was held between the staff and the NSP representatives, at the request of NSP, to discuss the contents of the staffs April 10,1998, RAl. By a letter dated May 15,1998, NSP documented its understanding

. of the April 29,1998, conference call with the staff. NSP's response to the staffs RAI dated April 10,1998 is pending generic resolution by the nuclear industry's collaborative effort.

Based on its review of the NSP's January 28,1997, submittal, the staff has the following RAI O concerning the issue of" thermally induced pressurization of piping runs penetrating the containment." In its submittal, NSP indicated that several piping segments penetrating containment, completely inside containment, and completely outside containment in each unit ,

were susceptible to thermally induced pressurization. NSP indicated that the pressurization of the segments was evaluated in a calculation identified as ENG-ME-299. The staff requests that NSP submit a copy of this calculation for the staffs review.

NSP also indicated that the pressurization in several piping segments was calculated based on a heat transfer analysis. The staff requests that NSP provide the following information for those penetrations, if it is not included in calculation ENG-ME-299:

Provide the applicable design criteria for the piping and the valves. Include the required load combinations; I

Provide a drawing of the piping run between the isolation valves. Include the lengths and thicknesses of the piping segments and the type and thickness of the insulation; 9810190164 981014 ,  !

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l R. O. Anderson 2* October 14, 1998 1

Provide the maximum calculated temperature and pressure for the pipe run. Describe,  ;

in detail, the method.used to calculate these pressure and temperature values. This l should include a discussion of the heat transfer model used in the analysis and the basis ,

for the heat transfer coefficients used in the analysis. I in addition, NSP indicated that for several piping segments, thermal pressurization would be {

relieved by valve leakage. Please provide the following inform'ation for those penetrations, if it is not included in calculation ENG-ME-299: l Describe the applicable design criteria for the piping and valves. Include the required load combinations; i

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Provide a drawing of the valve. Provide the pressure at which the valve was determined to lift off its seat or leak and describe the method used to estimate this pressure.

Discuss any sources of uncertainty associated with the estimated lift off or leakage pressure; '

Provide the maximum calculated stress in the piping run based on the estimated lift off or leakage pressure.

The above requested information was discussed with Mr. Gene Eckholt of your staff on l October 13,1998. ' A mutually agreeable target date of January 15,1999, for your response was established. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.

Sincerely, ORIGINAL SIGNED BY Tae Kim, Senior Project Manager Project Directorate lil-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket Nos: 50-282,50-306 cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD31 r/f EAdensam (EGA1)

OGC ACRS MKunowski, Rlli RWessman TMarsh JZwolinski GHammer JTatum DOCUMENT NAME:G:\WPDOCS\ PRAIRIE \GL9606.RAI *See previous concurrence To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy **No major changes to RAI 0FFICE PM PD31 lE LA:PD31 / lE LPM:PD31* l SC:EMEB** l PD:PD31 l6 NAME TJKim CJamerson @/ BWetret KManoly CAcarpenter [ F DATE 10//3/98 10/ 1 3 /98 // 9/30 /98 9/ 15 /98 10/ G /98

$fficial Record Copy l

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Mr. Roger O. Anderson, Director Prairie Islarid Nuclear Generating  !

Northern States Power Company _ Plant cc:

J. E. Silberg, Esquire - Site Licensing She,,, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W. Plant i Washington DC 20037 Northern States Power Company 1717 Wakonade Drive East j Plant Manager Welch, Minnesota 55089 l Prairie Island Nuclear Generating l Plant Tribal Council Northern States Power Company Prairie Island Indian Community 1717 Wakonade Drive East ATTN: Environmental Department l Welch, Minnesota 55089 5636 Sturgeon Lake Road l l Weich, Minnesota 55089  !

Adonis A. Nebiett  :

Assistant Attorney General l

Office of the Attorney General i 455 Minnesota Street '

Suite 900

< St. Paul, Minnesota 55101-2127 J

U.S. Nuclear Regulatory Commission Resident inspector's Office {

1719 Wakonade Drive East -

Welch, Mirnesota 55089-9642 )

Regional Administrator, Region 111  ;

U.S. Nuclear Regulatory Commission i 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Stephen Bloom, Administrator Goodhue County Courthouse i Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service i 121 Seventh Place East l Suite 200

St. Paul, Minnesota 55101-2145 June 1998 I

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