ML20134J685
| ML20134J685 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/13/1996 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Link R WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-M96697, NUDOCS 9611150340 | |
| Download: ML20134J685 (5) | |
Text
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November 13, 1996e
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PUBLIC JHannon Mr. Robert E. Link, Vice President PD3-1 Reading ACRS j
Nuclear Power Department JRoe JCaldwell, RIII Wisconsin Electric Power Company OGC EAdensam (E) 231 West-Michigan Street, Room P379 THuffert LBrown l
Milwaukee, WI 53201' JMcCormick-Barger, RIII l
l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON CONTROL ROOM HABITABILITY j
EVALUATION TO SUPPORT STEAM GENERATOR REPLACEMENT - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M96697, M96698,~M96741 and M96742)
Dear Mr. Link:
i As discussed with your staff.on October 18, 1996, the Nuclear Regulatory l
Commission noted that your submittal of August 5,1996, included a change in I
the' loss-of-coolant accident doses as described in Final Safety Analysis Report Section 14.2.4, " Radiological Consequences of a Steam Generator Tube Rupture Accident." 'To support an independent assessment of dose consequences as a result of changes in your plant design, the staff determined that additional information is required.
Please respond to Part A of the enclosed i
request for additional information (RAI) by November 20, 1996,. and Part B of the RAI by December 2, 1996.
If you have any questions, please contact me at (301) 415-1380.
Sincerely, A
^
Original -signed by.
Linda L. Gundrum,. Project-Manager Project Directorate,III-1
'A3 9611150340 961113 Division of Reactor Projects III/IV 1
DR ADOCK O 26 Office of Nuclear Reactor. Regulation Docket Nos. 50-266 and 50-301
Enclosure:
'NRC 'HLE CENTER COPY cc w/ encl:
See next page DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTBDOSE.RAI j
To,eoelve a copy of this document, indicate in the box: "C' = Copy without enclosures *E' = Copy with enclosures
- N" = No copy F
0FFICE PD31:PM
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,lE PD;1:PD Y I
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NAME LGundrum f t #-
CJamerson (M /
JHannon DATE 11/ r.t /96 11/12/96
//
11/l3/96 0FFICIAL RECORD COPY
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gp UNITED STATES g
g NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30666 4 001
\\*****/
November 13, 1996 Mr. Robert E. Link, Vice President i
Nuclear Power Department 1
Wiscorisin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee, WI 53201 i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON CONTROL ROOM HABITABILITY EVALUATION TO SUPPORT STEAM GENERATOR REPLACEMENT - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M96697, M96698, M96741 and M96742)
Dear Mr. Link:
As discussed with your staff on October 18, 1996, the Nuclear Regulatory Commission noted that your submittal of August 5,1996, included a change in the loss-of-coolant accident doses as described in Final Safety Analysis Report Section 14.2.4, " Radiological Consequences of a Steam Generator Tube i
Rupture Accident." To support an independent assessment of dose consequences l
as a result of changes in your plant design, the staff determined that additional information is required.
Please respond to Part A of the enclosed request for additional information (RAI) by November 20, 1996, and Part B of the RAI by December 2, 1996.
If you have any questions, please contact me at (301) 415-1380.
Sincerely, Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 i
and 50-301
Enclosure:
RAI cc w/ enc 1:
See next page i
=
Mr. Robert E. Link, Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company Unit Nos. I and 2 cc:
]
Ernest L. Blake, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mr. Scott A. Patulski, General Manager Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission I
of Wisconsin P.O. Box 7854 i
Madison, Wisconsin 53707-7854 i
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road l
Two Rivers, Wisconsin 54241 i
Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 I
J November 1996 l
j i
i REQUEST FOR ADDITIONAL INFORMATION ON CONTROL ROOM HABITABILITY EVALUATION TO SUPPORT STEAM GENERATOR REPLACEMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Part A I
1.
Describe,the modes of operation of the control room heating, ventilation, and air conditioning (HVAC) system, including the following: control room habitable volume in cubic feet, range of assumed flow rates (recirculated flow, fresh air inlet flow, filtered air flow) used for dose calculations, assumptions of inleakage and outleakage, pressurization assumed in inches of water gage and basis for assumption, descriptions of the filters used including assumed removal capabilities. Describe any additional protective measures included in calculation of control room dose.
2.
Define each postulated source term resulting from a control rod drop accident, steam generator tube rupture accident (SGTR), loss of reactor coolant flow accident (locked rotor), and main steam line break (MSLB).
Define the receptor points used for the control room, exclusion area boundary (EAB), and low population zone (LPZ).
Provide the following information for each source / receptor pair (plan view and cross-sectional figures may be helpful in describing the source, building configuration, and intake relationships):
a.
height of physical top of vent or stack or other assumed release
- point, b.
dimensions of buildings and other structures adjacent to or separating release point and intake / receptor, c.
horizontal straight line distance between source and receptor.
d.
height of physical intake or receptor, e.
direction (in degrees) from intake to source, as follows:
assuming one is standing at the intake looking toward the source, looking toward the North is 360*, toward the East is 90, toward the South is 180*, etc. This grid system must be congruent with the meteorological data collection grid system requested in Question 4.
I f.
An hourly listing of 5 years of onsite meteorological data representative of long-term conditions at the site. Data should be provided in a form consistent with the format described in Appendix A to section 2.3.3, "Onsite Meteorological Measurements Programs," of NUREG-0800, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition." Although reference is made to a magnetic tape, dv.a provided on other electronic media (e.g., a 31/2 inch dirk) will also be acceptable.
g.
Describe the mode of operation of the control room HVAC for each accident for the 30-day control room operator dose calculations.
ENCLOSURE i
j
! 3. What are the basis and assumptions for the X/Qs used in your past and current control room habitability assessments?
4.
What is the basis for the atmospheric dispersion estimates used in the dose assessment for the EAB, LPZ, and any other off-site locations? For each of the 16 compass directions, what is the minimum distance from each assumed release point to the site boundary or to the shoreline for those cases in which the site boundary extends past the shorelinc?
Part B Analyze the following accidents:
(1) steam generator tube rupture, (2) control rod ejection, (3) locked rotor, and (4) main steamline break.
Submit a copy of your accident analysis report that contains the calculated control room, EAB and LPZ doses and a comparison of the results to the 10 CFR 1
Parts 50 and 100 acceptance criteria. Also provide sufficient documentation l
of your analyses to support an independent evaluation, such as the code inputs, the references for the code inputs (e.g., UFSAR or new docketed analyses), and the dose calculations.
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