ML20141M404

Requests Addl Info in Order to Complete Review of Util 901023 Request Revising Required Water Temp & Monitoring Elevation of Plant Standby Nuclear Svc Water Pond

ML20141M404
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/05/1992
From:	Tim Reed Office of Nuclear Reactor Regulation
To:	Mcmeekin T DUKE POWER CO.
References
TAC-M79018, TAC-M79019, NUDOCS 9208130160
Download: ML20141M404 (4)

Text

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August 5, 1992 I Docket Nos. 50-369 and 50-370 Mr. T. C. McMeekin Vice President, McGuire Site Duke Power Company 12700 Hagers Ferry Road Huntersville, North Carolina 28078-8985

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - STANDBY NUCLEAR SERVICE WATER POND TEMPERATURE MONITORING REQUIREMENTS (TAC N05. M79018/M79019) _

The NRC staff is reviewing Duke Power Company's request to revise the required water temperature and monitoring elevation of the McGuire Standby Nuclear Service Water Pond submitted on October 23, 1990. We find that we need additional information in order to complete our review. Accordingly, please respond to the questions identified in the enclosure. If you have any questions concerning this request, please contact me at (301) 504-1479.

This request affects fewer than ten respondents ana is, therefore, not subject to Office of Management & Budget review under P.L.96-511.

Sincerely,

/s/

Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects-l/II -

Office of Nuclear Reactor Regulation

Enclosure:

DISTRIBUTION: SVarga As stated . Docket 1 File. Glainas NRC & Local PDRs ACRS (10), P-315 cc w/ enclosure: PDII-3 R/F EJordan MNBB3701 See next page McGuire R/F 0GC, 15B18 LBerry LReyes, RII Treed DMatthews DShum, 801 I.

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Docket Nos. 50-369 and=50-370 Mr.HT. C. McHeekin Vice President, McGuire Site <

Duke: Power Company _.

-12700_Hagers Ferry Road Huntersville, North Carolina 28078-8985

Dear Mr. McHeekin:

1

SUBJECT:

' REQUEST FOR ADDITIONAL-INFORMATION-- STANDBY NUCLEAR SERVICE WATER *

. POND TEMPERATURE MONITORING _ L QUIREMENTS (TAC NOS. M79018/M79019)-

.Th'e-NRC-staff is reviewing Duke Power Company's request to revise the required-water .temperatureiand monitoring elevation of the McGuira Standby Nuc? ear Service Water Pond submitted on,0ctober 23, 1990. - We find-that we need

~a dditionallinformation in order:to complete our _ review. Accordingly, please

. respond to the question's identified in _the-enclosure. ' If you_ have any questions'concerning:this-request, please~ contact me at (301)-504-1479.

This' request affects' fewer than ten respondents and is, therefore, not subject-

-:-to-Office;ofL Management & Budget review under P.L.96-511.

Sincerely,-

Timothy A.' Reed,4 Project-Manager

. Project Directorate'11-3

- Division of Reactor. Projects-1/II Office of. Nuclear Reactor Regulation

Enclosure:

As-stated-

'cc;w/ enclosure: -

lSee'next page-h-

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+r-a m. .r. e $ w. - - y e.- y y 9

o Mr. T. C. McHeekin Duke Power Company McGuire Nuclear Station cc:

Mr. A. V. Carr, Esquire Mr. Dayne H. Brown, Director Duke Power Company Department of Environmental, 422 South Church Street Health and Natural Resources Charlotte, North Carolina 28242-0001 Division of Radiation Protection P.-0. Box 27687 County Manager of Mecklenberg County Raleigh, North Carolina 27611-7687 720 East Fourth Street Charlotte, North Carolina 28202 Mr. Ah9n R. Herdt, Chief Project Branch #3 Mr. R. O. Sharpe U. S. Nuclear Regulatory Commission Compliance 101 Marietta Street, NW. Suite 2900

' Duke Power Company Atlanta, utirgia 30323 McGuire Nuclear Site 12700 Hagers Ferry Road Ms. Karen E. Long Huntersville, NC 28078-8985 Assistant Attorney General North Carolina Department of J. Michael McGarry, III, Esquire Justice Winston and Strawn P. O. Box 629 1400 L Street, NW. Raleigh, North Carolina 27602 Washington, DC 20005 Mr. R. L. Gill, Jr.

Senior Resident-Inspector Licensing c/o V. S. Nuclear Regulatory Duke Power Company Commission P. O. Box 1007 12700 Hagers Ferry Road Charlotte, North Carolina 28201-1007 Huntersviile, North Carolina 28078 Regional Administrator, Region II Mr. Frank Modrak U.S. Nuclear Regulatory Commission Project Manager,-Mid-South Area 101 Marietta Street, NW. Suite 2900

-ESSD Projects: Atlanta, Georgia 30323 Westinghouse. Electric Corporation MNC~ West Tower - Bay-241 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Dr. John M. Barry Mecklenburg County Department of Environmental Protection-700 N. Tryon Street Charlotte, North Carolina 28202

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION STANDBY NUCLEAR SERVICE WATER POND TEMPERATURE MONITORING REQUIREMENTS

1. FSAR page 6-162 indicates that the containment spray pump runout flow is 4800 gpm, while FSAR page 6-553 indicates that containment spray pump runout is 3400 gpm. Which value is correct and which wa:> used in the containment peak pressure analysis? How does this value relate to Table 6.2.1-18?

2. FSAR page 6-553 indicates that the runout flow for the RHR pump is 4500 gpm which is inconsistent with other data available. What is the correct RHR pump runout flow? Provide a pump curve (including a system curve) to show the design point and actual operating point for the RHR pump.

3. DPC has indicated that site functional tests were performed to determine the RHR pump flow during the recirculation phase of a postulated loss-of-coolant accident (LOCA). What were the objectives and results obtained from the site functional tests (i.e., flow rates, flow resistence,etc.)? With approximately 2500 gpm diverted to auxiliary containment spray, what is the flow (measuied or calculated) remaining for ECCS during the recirculation portion of the LOCA?

4. i,

• March 3, 1992, response indicates that heat exchanger fouling has reduced the containment heat exchanger UA (from 2.94 to 1.47 E06 Btu /hr-F) and the component cooling water heat exchanger UA (from 5.0 to 1.6 E06 Btu /hr-F). This is a substantial change that should affect the analysis results. Please provide the significant analysis inputs and the corresponding analysis results for the containment peak pressure analysis that supports the subject TS submittal . Identify the inputs -

that were changed as part of the containment peak preaure analysis and to the extent possible (recognizing that when several analysis parameters are changed it becomes difficult to quantitatively identify the impact each individual change has on the calculated containment peak pressure) discuss the impact that analysis input changes had on the analysis results.

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