ML20136B536
| ML20136B536 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/04/1997 |
| From: | Hill W NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20136B539 | List: |
| References | |
| TAC-M97781, NUDOCS 9703110018 | |
| Download: ML20136B536 (3) | |
Text
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Northem Str.*as Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello. Minnesota 55362-9637 March 4,1997 US Nuclear Regulatory Commission 10 CFR Part 50 Attn: Document Control Desk Section 50.90 Washington, DC 20555 TAC No. M97781 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Supplement No.1 to License Amendment Request Dated January 23,1997 Uodate of Desian Basis Accident Containment Temoerature and Pressure Resoonse Attached is a supplement to our January 23,1997, request for an amendment to the Technical Specifications, Appendix A of the Operating License, for the Monticello Nuclear Generating Plant.
j The purpose of this supplement is to respond to an NRC letter dated Pobruary 21,1997, "Monticello Nuclear Generating Plant - Request for Additional Inform ion on License Amendment Request Dated January 23,1997 entitled Update of Design Basis Accident 1
Containment Temperature and Pressure Response (TAC No. M97781)".
Our response to your February 21,1997 request is contained in the following attachments to this letter:
Question No.1 Attachments 1,2, and 3 Question No. 2 Question No. 3 This submittal contains no new NRC commitments, nor does it modify any prior commitments.
0 9703110018 970304 ADOCK0500g3 g
Response to USNRC Request for Additional Information March 4,1997 Page 2 l
Please contact Mr Samuel Shirey, Sr Licensing Engineer, at (612) 295-1449 if you require additionalinformation related to this request.
Y'S b
William J Hill Plant Manager Monticello Nuclear Generating Plant
)
c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident inspector, NRC Siate of Minnesota Attn: Kris Sanda J Silberg, Esq.
Attachments:
1)
Emergency Core Cooling System Net Positive Suction Head 2)
Torus Attached Piping Evaluation 3)
Evaluation of RHR Room Temperature During DBA LOCA 4)
Evaluation of Nuclear Containment Insulation System
)
5)
NEDO-32418, Source of input Parameters i
l i
l UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
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REQUEST FOR AMENDMENT TO OPERATING LICENSE DPR-22 SUPPLEMENT NO.1 TO LICENSE AMENDMENT REQUEST DATED JANUARY 23,1997 Northern States Power Company, a Minnesota corporation, is submitting Supplement No.1 to License Amendment Request dated January 23,1997. This supplement responds to NRC Staff questions.
This letter contains no restricted or other defense information.
i NORTHERN STATES POWER COMPANY By.
William J Hifi Plant Ma7ager Monticello Nuclear Generating Plant ay of brck
. NM before me a notary public in and for said County, On this personally appeared Wi'liam J Hill, Plant Manager, Monticcib Nuclear Generating Plant, and being first duly sworn acknowledged that he is authoriz.ed to execute this document on behalf of Northern States Power Company, that he knows the cordents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
SAMUEL 1. SMNIEY l
NOTARY PUGUC bEMMOR Samuel i Shirey
_ _, _ yy comm. co. Jen. st, asool Notary Public - Minnesota Sherburne County My Commission Expires January 21,2000
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Response to USNRC Request For AdditionalInformation l
March 4,1997 j
Attachment i 1
1' i
SUPPLEMENTAL INFORMATION FOR LICENSE AMENDMENT REOUEST l
DATED JANUARY 23.1997 EMERGENCY CORE COOLING SYSTEM NET POSITIVE SUCTION HEAD i
Refer to the attached calculation package prepared by Duke Engineering & Services for the Monticello Nuclear Generating Plant, " Low Pressure Emergency Core Cooling L.
System (ECCS) Net Positive Suction Head (NPSH)," Calculation No. V609.000.00001, f
Four cases were evaluated as follows:
1-l Case Pumps In Operation
-Wetwell Chamber Suppression Pool i
Pressure Assumptions Temperature j.
Assumptions 1 - Short Term 4 RHR Pumps Wetwell pressure at Wetwell temperature -
i 2 Core Spray Pumps t=10 minutes with
' at t=10 minutes of i
at Runout Flow methodology to 147 F
[
minimize pressure i
2 - Short Term 4 RHR Pumps Wetwell pressure at Wetwell temperature 2 Core Spray Pumps 50% of NEDO-32418 at t=10 minues of j.
at Runout Flow at t=10 minutes 147 F i
3 - Long Term i RHR Pump Wetwell pressure at Peak wetwell I Core Spray Pump peak temperature with temperature of 184*F i
methodology _to minimize pressure t
4 - Long Term i RHR Pump Wetwell pressure at Peak NEDO-32418 1 Core Spray Pump 50% of NEDO-32418 wetwell temperature at time of peak of 184 F temeprature References and detailed computer output cited in the attached report are available for inspection at the Monticello Plant.
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