ML20134P479

Forwards RAI to Complete Review of NSP Submittal of License Amend Requesting Review & Approval of Update to Design Basis Accident Containment Temp & Pressure Response

ML20134P479
Person / Time
Site:	Monticello
Issue date:	02/21/1997
From:	Kim T NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
TAC-M97781, NUDOCS 9702250486
Download: ML20134P479 (4)

Text

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. . . February 21, 1997 Mr. Roger 0. Anderson, Director Distribution:

Licensing and Management Issues Dock;t File- OGC Northern States Power Company PUBLIC AGill 414 Nicollet Mall PD3-1 Rdg. JKudrick i Minneapolis, MN 55401 JRoe KKavanagh s

EAdensam(EGA1) ACRS JJacobson, DRP/RIII

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST DATED JANUARY 23, 1997 ENTITLED UPDATE OF DESIGN BASIS ACCIDENT CONTAINMENT TEMPERATURE AND PRESSURE RESPONSE (TAC'N0. M97781)

Dear,

Mr.' Anderson:

By letter dated 7 January'23, 1997,_and as revised by letter dated January 28, i 1997, Northern States Power Company (NSP) submitted a license amendment i requesting review and approv'al of an update to the design basis accident containment' temperature and pressure response.

Based on a preliminary review of the above submittals, the staff has l determined that additional information is necessary to complete its review. l The enclosed request for additional information (RAI) provides details of the {

required material..  !

l Please provide your response within 60 days of the date of this letter. If you need additional time, or if you have any questions, please contact me at (301) 415-1392.

Sincerely, Original signed by: )

Tae Kim, Senior Project Manager Project Directorate III-l Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation i

Docket No: 50-263

Enclosure:

As stated cc w/ encl: See next page DOCUMENT NAME: G:\WPDOCS\MONTICEL\ MON 97781.RAI To receive a copy of this document, indcate in the box: "C" = Copy without enclosures *E" = Copy with enclosures *N*

= No copy 0FFICE PD31:PM lE PD31:LA lE PD31:PQ /gG l NAME TJKim -7$ E CJamerson 0b JHannoWD/s DATE 2/zd97 " 2/19 /97 // 2/7C/97 F d 0FFICIAL RECORD COPY l

25 coy pg jggmIEit CDPV 9702250486 970221 DR ADOCK0500g3

a ux jf t" UNITED STATES NUCLEAR REGULATORY COMMISSION  ;

O ;E WASHINGTON, D.C. 2056H001 I

\ *****j/ February 21, 1997 Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST DATED JANUARY 23, 1997 ENTITLED UPDATE OF DESIGN BASIS ACCIDENT CONTAINMENT TEMPERATURE AND PRESSURE RESPONSE (TAC NO. M97781)

Dear Mr. Anderson:

By letter dated January 23, 1997, and as revised by letter dated January 28, 1997, Northern States Power Company (NSP) submitted a license amendment  ;

requesting review and approval of an update to the design basis accident i containment temperature and pressure response.

Based on a preliminary review of the above submittals, the staff has determined that additional information is necessary to complete its review.

The enclosed request for additional information (RAI) provides details of the required material. -

Please provide your response within 60 days of the date of this letter. If you need additional time, or if you have any questions, please contact me at (301) 415-1392.

Sincerely,

/ /

b/k-)~~~

Tae Kim, Senior Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No: 50-263

Enclosure:

As stated cc w/ encl: See next page

- . o ,

Mr. Roger 0. Anderson, Director Monticello Nuclear Generating Plant Northern States Power Company cc:

J. E. Silberg, Esquire Adonis A. Neblett Shaw, Pittman, Potts and Trowbridge Assistant Attorney General 2300 N Street, N. W. Office of the Attorney General

Washington DC 20037 445 Minnesota Street Suite 900 U.S. Nuclear Regulatory Commission St. Paul, Minnesota 55101-2127 Resident Inspector's Office 2807 W. County Road 75 Monticello, Minnesota 55362 Plant Manager Monticello Nuclear Generating Plant ATTN

Site Licensing Northern States Power Company 2807 West County Road 75 Monticello, Minnesota 55362-9637 i

Robert Nelson, President Minnesota Environmental Control Citizens Association (MECCA) 1051 South McKnight Road ,

St. Paul, Minnesota 55119 Comissioner Minnesota Pollution Control Agency i 520 Lafayette Road  !

St. Paul, Minnesota 55119 Regional Administrator, Region III U.S. Nuclear Regulatory Comission 801 Warrenville Road Lisle, Illinois. 60532-4351 Comissioner of Health Minnesota Department of Health 717 Delaware Street, S. E.

Minneapolis, Minnesota 55440 i

Darla Groshens, Auditor / Treasurer Wright County Government Center <

10 NW Second Street Buffalo, Minnesota 55313 Kris Sanda, Comissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 uom im

_ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ - _ - - - ~ ~ - ---

4

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REQUEST FOR ADDITIONAL INFORMATION I MONTICELLO NUCLEAR GENERATING PLANT I i

1. " Revision No. I to License Amendment Request Dated January 23, 1997  !

Update _of Design Basis Accident Containment Temperature and Pressure Response," dated January 28, 1997, stated that the emergency core (

cooling system (ECCS) pump net positive suction head (NPSH), wetwell '

attached piping, and environmental conditions in the ECCS pump rooms j have all been evaluated and found to be acceptable for the slightly higher suppression pool temperature. Please provide the results of the ,

evaluations including copies of the ECCS pump NPSH calculations for the e staff review.

~

2. The proposed Technical Specification Bases state that " acceptable  :

margins to containment design conditions have been demonstrated....  !

Therefore the containment spray / cooling system is more than ample to '

provide the required heat removal capability." Surveillance ,

requirements also provide added assurance that the containnent spray / cooling system will be available when required. However, post-LLOCA [ loss-of-coolant accident] conditions are not the same as normal operations and surveillanse conditions. Section 6.2.1.2 of the USAR

[ updated safety analysis report] states that "the post LOCA'long-term  ;

operability of the core spray and RHR [ residual heat removal] pumps is <

enhanced by the use of Nukon insulation exclusively inside the drywell. <

Nukon has been tested for compliance with Reg. Guide 1.82, Rev. 1,

[ Water Sources for Long-Term Recirculation Cooling Following a Loss-if-  ;

Coolant Accident]... to assure that displaced insulation does not  :

collect at the pump. inlet debris screen and impede the positive suction )

head of the pumps." Has an evaluation been performed to verify that the  ;

Nukon will not impede the ability of the containment spray / cooling  !

system to perform its required function post-LOCA? If so, please  !

provide a copy of the analysis to the staff. 1

3. Table 2-1 in Exhibit D of the license amendment request dated January 23, 1997 lists the input parameters for the containment analysis. Please provide the source (i.e., technical specifications, UFSAR [ updated final safety analysis report], or other licensing basis documents) for each input value listed in the table.

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