ML20058L236
| ML20058L236 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/30/1993 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9312160199 | |
| Download: ML20058L236 (6) | |
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UNITED STATES-
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j NUCLEAR AEGULATORY COMMISSION l
WASHINGTON, D.C. 20li66-0001 l
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November 30, 1993 4
j Docket No.52-003
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Mr. Nicholas J. Liparulo 1
Nuclear Safety and Regulatory Activities i
Westinghouse Electric Corporation 4
P.O. Box 355 Pittsburghi Pennsylvania 15230 j
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Dear Mr. Liparulo:
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI)'ON THE AP600 i
-i The staff has contracted with Idaho National Engineering Laboratory-(INEL) to -
i have them develop a QA version of the SPES-2 RELAPS input deck to support the staff's review of the design certification application for'the AP600. As a result of its meeting with Westinghcuse on October 4, 1993,-and further internal review of the information provid additional information (Q952.29-Q952.36).pd, INEL has determined that it needs Enclosed are the staff's ques.
i tions. Please respond to this request within'90 days of the date of receipt of this letter.
I You have requested that portions of the information submitted in the. June 1992 j
d application for design certification be exempt from mandatory public disclo-While the staff has not completed its review of your request-in sure.
accordance with the requirements of 10 CFR 2.790, that portion of the submit--
ted information is being withheld from public disclosure pending the staff's g
i final determination. The staff concludes that this request for. additional-information does not contain those portions of the information' for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westing-l
~
house the opportunity to verify the staff's conclusions.
If, after that tirae, you do not request that all or portions of the information in the enclosures i
be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission's Public Document i
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.The numbers in parentheses designate the tracking numbers assigned'to the questions.
9312160199 931130 PDR ADOCK 05200003
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E CNS NY 13002a i
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Mr. Nicholas J. Liparulo November 30, 1993
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This RAI affects nine or fewer respondents, and therefore, is not subject to review by the Office of Management and Budget under P.L.96-511.
If you have any questions regarding this matter, you can contact me at (301) 504-1120.
Sincerely, (Original signed by)
Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
j As stated cc w/ enclosure:
See next page DISTRIBUTION-
- Central File PDST R/F TMurley/FMiraglia DCrutchfield
- PDR WTravers RBorchardt RArchitzel TKenyon RHasselberg BDean, ED0 JMoore, 15B18 MSiemien, 15818 Alevin, BE23 GHsii, 8E23 PShea TCollins, 8E23 JKelly, RES ACRS (11) w/o enc 1.
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LA:PDST:ADAR PM:PdS ;ADAR SRXB Y SC:PDST:dDAR NAME:
PShea 3 6 T[enNrf:sg RJones b RArchitzel 11/d/93 11/6'//93 11/NZ'/93 DATE:
IM'93 0FFICIAL RECORD COPY:
DOCUMENT NAME: SPES2.RAI i
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i Mr. Nicholas J. Liparulo Docket No.52-003 Wec'inghouse Electric Corporation AP600
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cc:
Mr. B. A. McIntyre Advanced Plant Safety & Licensing l
Westinghouse Electric Corporation l
Energy Systems Business Unit i
i P.O. Box 355 i
l Pittsburgh, Pennsylvania 15230
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Mr. John C. Butler Advanced Plant Safety & Licensing 1
Westinghouse Electric Corporation Energy Systems Business Unit l
Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 i
Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.
20585 Mr. S. M. Modro EG&G Idaho Inc.
Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner i
725 17th Street, N.W.
Room 8002 Washington, D.C.
20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 Mr. Victor G. Snell, Director Safety and Licensing AECL Technologies i
9210 Corporate Boulevard Suite 410 Rockville, Maryland 20850 6
REQUEST FOR ADDITIONAL INFORMATION ON THE WESTINGHOUSE AP600 DESIGN 952.29 Provide all the bend / elbow radius in the following piping systems of the SPES-2 facility (all page numbers refer to Dwg. 00189DD92)-
a.
Downcomer-Upper Head bypass (pg. 30):
2 elbows
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b.
Pressurizer to CMT balance lines (pg. 31):
11 elbows c.
Cold Leg to CMT balance lines (pg. 32):
13 elbows d.
CMT Discharge lines (pg. 33):
10 elbows 4 bends e.
IRWST Injection lines (pg. 34):
14 elbows l
f.
PRHR HX, Supply line, Return line (pg. 35):
7 elbows
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g.
Accumulator Injection lines (pg. 36):
8 bends or elbows 952.30 Provide the type and size of valves in the following piping systems of the SPES-2 facility (all page numbers refer to Dwg. 00189DD92):
l a.
Downcomer-Upper Head bypass (pg. 30):
1.
Isolation valve at Elevation +1425 b.
Pressurizer to CMT balance lines (pg. 31):
1.
Check valve in piping run from Elevation +10714 to Elevation +10528 (to CMT-A).
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2.
Check valve in piping run from Elevation +10911 to Eleva-tion +10734 (to CMT-B).
c.
Cold Leg to CMT balance lines (pg. 32):
1.
Air operated valve in piping run from Elevation +5833 to Elevation +5970 (to CMT-B).
2.
Air operated valve in piping run from Elevation +5881 to Elevation +6027 (to CMT-A).
d.
CMT Discharge lines (pg. 33):
1.
Motor operated valve in piping run at Elevation -791 (from CMT-A).
1 2.
Motor operated valve in piping run at Elevation -791 (from CMT-B).
Enclosure
O t
i e.
IRWST Injection lines (pg. 34):
i 1.
Isolation valves just below the IRWST (both lines).
i 2.
Check valves in piping run from Elevation -991 to Elevation -
508 (both lines).
f.
PRHR HX, Supply line, Return line (pg. 35):
1.
Air operated valve in piping run at Elevation +8026 (Supply line),
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i 2.
Motor operated valve in piping run at Elevation +2667 (Return line).
i g.
Accumulator Injection lines (pg. 36):
)
1.
Two air operated valves in piping run from Elevation -3569 to Elevation -508 (one in each accumulator injection line).
i 952.31 Provide updated and complete schematics / plant drawings for the follow-ing systems of the SPES-2 facility. The exact locations and lengths of the valves or flow meters in these systems should be clearly visible in the schematics.
a a.
PRHR Supply, Heat Exchanger, and Return lines.
b.
ADS Stage 1, 2, 3, and 4 inlet, valve nest,. and discharge piping lines.
i c.
CMT Discharge line.
d.
IRWST Injection line.
I e.
Steam Generators, in particular the separator bypass.
i 952.32 Clarify /specify the following operational parameter 3 or particular f
component operation:
a.
Is the leakage power of 1.3 percent from the power rod cable runs through the lower plenum a portion of the total power of 4.9 MW or additive to the total power?
b.
Provide the steam generator's ~ steady-state secondary water levels, secondary water mass, recirculation ratios, and riser inlet temperatures.
Provide the pressurizer's steady-state water level, the power c.
inputted into the pressurizer using the external heaters, and the s
control logic for these external heaters.
d.
Provide the initial PRHR valve positions and operations during tests involving the PRHR system.
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e.
Provide the ADS valves' rated flows and pressure drops, and for a given flow, the pressure drops from the ADS valves to their respective catch tanks.
I f.
Provide the expected heat transfer rate from the CMTs to their l
outer tank.
In particular, the pressure and temperature of the air surrounding the CMTs and what control systems will be used to control the temperature and pressure in this outer tank.
I g.
Provide the expected volume and fluid. temperature of the Lower Plenum that will become stagnant at the very bottom of the pres-sure vessel.
952.33 Clarify the position relationship of the pressure vessel connections of DVI A and B with respect to the pressure vessel cold leg nozzle attachment locations.
Is DVI A between Cold Legs A2 and B1 or between l
Cold Legs B2 and Al?
952.34 Provide the following information on the SPES-2 test procedures, a.
The location, size, and geometry for all breaks.
b.
Which ADS 4th stage valve will be failed?
c.
Which CMT will be failed?
952.35 Provide information on the insulation material, thickness, and lengths for the entire SPES-2 facility. This request is in addition to
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previous inquiries on the measured heat losses of the SPES-2 facility
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(Letter from N. J. Liparulo, Westinghouse, to R. W..Borchardt, NRC, dated August 13,1993).
952.36 Page 8 of Dwg. 00189DD92 shows a cross-section of the upper plenum and annular downcomer in the SPES-2 facility. -The 8 circumferential pressure drop fin: and the 2 hot leg baffle plates can be seen.
However, there are 4 other structures shown in'this cross-sectional view that correspond to the same vessel azimuthal angles as the cold leg nozzles. What are these devices, their physical dimensions (including elevation in the annular downcomer), and their purpose in the SPES-2 facility, including their relationship to any feature or expected phenomena in AP600's downcomer or vessel?
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