ML20035G589
| ML20035G589 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 04/13/1993 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9304280129 | |
| Download: ML20035G589 (7) | |
Text
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[p ung'o UNITED STATES
! )g ' ~,,g NUCLEAR REGULATORY COMMISSION E
WASWNG TON, D. C. 20555 8
3 April i3,1993
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Docket No.52-003 l
Mr. Nicholas J. Liparulo 4
i Nuclear Safety and Regulatory Activities l
)
Westinghouse Electric Corporation l
l P.O. Box 355 Pittsburgh, Pennsylvania 15230 i
Dear Mr. Liparulo:
l l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE AP600 As a result of its review of the June 1992, application for design certifica-l tion of the APo00, the staff has determined that it needs additional informa-tion in order to complete its review.
The additional information is needed in the areas of structural engineering (Q220.21-Q220.23),* containment systems (Q280.4), and radiation protection (Q471.4-Q471.20).
Enclosed are the staff's questions.
Please respond to this request within 120 days of the date of l
receipt of this letter.
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's 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 Westinghouse the opportunity to verify the staff's conclusions.
If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.
- The numbers in parentheses designate the tracking numbers assigned to the questions.
()0 9304280129 930413 1\\ _ h da
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Mr. Nicholas J. Liparulo April 13, 1993 This request for additional information affects nine or fewer respondents, and therefore is not subject to review by the Office of ';nagement and Budget review under P.L.96-511.
If you have any questions regarding this matter, you can contact me at (301) 504-1120.
Sincerely, Ongh!grgny y Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
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04//jlS3 04/1)/93 04/fS/93 04//;3/9i4 0FFICIAL RECORD COPY:
DOCUMENT NAME: LTR_8.RAI m6 4
Mr. Nicholas J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 cc:
Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing l
Westinghouse Electric Corporation Energy Systems Business Unit 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 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 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 as
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REQUEST FOR ADDITIONAL INFORMATION I
ON THE WESTINGHOUSE AP600 DESIGN
)
l Structural Engineering 220.21 The last paragraph in Section 3.3.1.1 of the SSAR states that
" Vertical velocity profiles and gust response factors are calculated according to [the American Society of Civil Engineers (ASCE), 7-88 (formerly ANSI A58.1-82), " Minimum Design Loads for Buildings and Other Structures") for exposure D.
This is the most severe of the four cases specified in [ASCE 7-88]."
The most severe cases appear to be the combination of the gust response factors with exposure A and the velocity pressures with exposure D for the velocity pressure exposure coefficient of K,.
In the case of velocity pressure "q,,"
exposure D gives higher values of q This reversal of the influence ofexposurecategoriesintermsof[.he q, and gust response factors can be confusing.
For the standard design, the exposure categories can vary.
Therefore, provide the actual wind force profiles to be used for the standard design for the various shapes of the structures.
The applicant for a combined operating license (COL) will have to compare the site-specific wind force profile to the design wind force profile.
1 Calculations of vertical velocity profiles with exposure D are not given in ASCE 7-88.
Provide the actual vertical velocity profiles to be used for the standard design for the various shapes of the structures.
The COL applicant will have to compare the site-specific vertical velocity profile to the design vertical velocity profile.
220.22 Section 3.5.1.4 of the SSAR describes a missile with a vertical l
velocity of 74 mph. This is 70% of the postulated horizontal velocities for a 1,800 kg (4,000 pounds) automobile and a 125 kg (275 pound), 20.32 cm (8 inch) shell as recommended in Section 3.5.1.4 of the SRP. However, the tornado missiles specified in Table 2.0-1 do not have these vertical velocities for a 1,800 kg (4,000 pounds) automobile and a 125 kg (275 pounds), 20.32 cm (8 inches) shell.
Specify these vertical velocities in Table 2.0-1 or redefine the tornado missiles as Spectrum I as specified in Section 3.5.1.4 of the SRP.
220.23 Section 3.5.3 of the SSAR provides formulae for mistile penetration calculations into steel or concrete barriers.
Also, it states that "Due to the conservative nature of these assumptions, the minimum thickness required for missile shields is taken as the thickness just perforated." However, Table 1 in Section 3.5.3 of the SRP specifies the minimum acceptable barrier thickness requirement for local damage prediction against tornado generated missiles.
Explain how the AP600 design complies with this guideline.
VH2i@iOMCEWr4RL4'ad14
. Containment Systems 280.4 Provide the test data for the passive containment cooling system that was generated from both the small and large scale test facilities that are related to dry shell testing conditions.
Radiation Protection 471.4 Section 12.1.1.1 of the SSAR states that pipes containing radioactive fluids or radioactive sources are adequately shielded and properly routed to minimize exposure to personnel.
Indicate and describe on area maps all radioactive horizontal pipe chases and areas that contain radioactive piping that personnel could come in contact with.
471.5 Sections 12.1.2.2 and 12.1.2.3 of the SSAR state that facility design considerations (modularization) to minimize the amount of personnel time spent in a high radiation area include the transportation of equipment or components requiring service to a lower radiation area.
List and describe the location of all major components and equipment that are designed to be transported to a lower radiation area during servicing.
471.6 Section 11.5.6.1 of the SSAR describes the design objectives of area radiation monitors (ARMS) and Table 11.5-2 of the SSAR describes the locations of the ARMS throughout the plant.
Describe the rational for the locations and numbers (which seem low compared with industry norms) of the ARMS that are required. Also, compare this rational with Criteria 4.2 (detector locations) of ANSI /ANS Standard HPSSC-6.8.1-1981 (Location and Design Criteria for Area Radiation Monitoring Systems for Light Water Nuclear Reactors), and justify any deviations.
471.7 Section 12.3.1.1.1 of the SSAR states that the steam generator i
manways are sized for easier entrance and exit of workers with
)
protective clothing, and to facilitate the installation and removal l
of tooling.
Provide the size of the manways and discuss the ease of l
personnel entering and exiting the steam generators while wearing full face air-supplied hooded respirators.
l 471.8 Section 12.3.1.1.1 of the SSAR states that tanks are provided with overflow lines diverted to waste collection systems to collect contamination within plant structures. Describe the arrangement of l,
the overflow lines into the waste collection system. Are they hard-piped into a sump, directed to a funnel, ar directed to a floor drain channel?
l 471.9 Section 12.3.1.1.1 of the SSAR states that floor drains are provided for each room or cubical containing serviceable components that contain radioactive liquids.
Describe how any high airborne l
l
l
, radioactive material is prevented from exiting these rooms through the floor drain system and spreading into other areas or rooms in the plant.
471.10 Section 12.3.1.1.1 of the SSAR states that multiple electric lights are provided for each cell or room containing highly radioactive components.
Is sufficient lighting provided in high radiation areas in the auxiliary building and containment to reduce the need to rig temporary lighting / power during maintenance periods or outages?
Justify your answer.
471.11 Section 12.3.1.1.1 of the SSAR discusses heating, ventilation and air-conditioning considerations.
Is sufficient ventilation provided during periods of maintenance or outages to provide personnel in high radiation areas with adequate cooling without having to run temporary ventilation, use exhaust blowers or require personnel to wear ice vests? Justify your answer.
4/1.12 Section 12.3.1.1.1 of the SSAR states that components exposed to high temperature reactor coolant contain specific limitations on the cobalt impurity content as give in Table 12.3-1 of the SSAR.
The table states that for bearings and hard-facing materials, the maximum weight percent average value is approximately 60.
Explain why this value is so high compared to the cobalt limitation for other components.
471.13 Section 12.3.1.1.1 of the SSAR states that the head closure system is designed to minimize the reactor head stud tensioning time.
Describe in more detail the operation of the system in tensioning and detensioning the head studs.
Include a breakdown of the estimated time and person-rem for each portion of this operation.
471.14 Section 12.3.1.2 of the SSAR states that Radiation Areas and High Radiation Areas will be posted and controlled.
No mention is made of Very High Radiation Areas as defined in 10 CFR 20.1602.
Provide the location of any areas where personnel could be exposed to radiation levels greater than 100 Rads in one hour as stated in the Standard Review Plan, and describe any special controls to prevent personnel entry in to these areas.
Also, Section 12.5.4 of the SSAR states the entrances to High Radiation Areas are equipped with audible and/or visible alarms.
Clarify this statement. Will these areas also be locked? Discuss how the requirements of 10 CFR 20.1601, " Control of Access to High Radiation Areas," and 10 CFR 20.1602, " Control of Access to Very High Radiation Areas," and the guidance of Regulatory Guide 8.38 (issued in May 1993) will be implemented.
471.15 Section 12.3.3.3.2 (1) of the SSAR states that atmospheric tanks that contain radioactive materials are vented to the building ventilation systems for filtration prior to release.
List all the tanks that are vented to the building ventilation systems.
.. 471.16 Section 12.4.1.1 of the SSAR states that, based on review of current plant operations, and on AP600 design changes and reliability improvements, it is estimated that 100 worker-hours per year are required to be spent in the containment to monitor the plant during power operations. Justify this 100 work-hour estimate and describe in detail the types of operations that it covers Describe what protective equipment will be needed (respirators, ice vests, etc.)
for the containment entries, and also include person-rem estimates of these operations.
471.17 Section 12.5.3.7 of the SSAR states that special coatings are applied to the walls and floors of areas containing radioactive fluids to aid in decontamination. Describe which areas of the plant will be treated with these coatings, and, if the entire wall surface will not l
be treated, describe how far up the walls these coatings will be 1
applied.
l 471.18 Section 9.3.1 of the SSAR describes the breathing air system (BAS) as l
l a subsystem of the compressed and instrument air system (CAS).
Describe the location of the suction of the CAS air compressors and describe how the air quality requirements of Paragraphs 20.1001-
'0.2401(2)(d) of Appendix A to 10 CFR 20 are met.
Describe what precautions are taken to prevent the CAS/ BAS from becoming cross-connected with other systems (e.g., waste gas or low pressure nitrogen systems). Also, describe the locations of these BAS service connections inside the containment relative to operations that will necessitate persennel use.
471.19 Figures 1.2-30 and 1.2-31 of the SSAR show areas around the steam generator blowdown heas exchangers, CCS pumps and heat exchangers, and the condensate polishing unit that would add future shield walls, if required.
Describe what future events or conditions would require the addition of additional shielding in these areas.
Also, provide the expected radiation levels in these areas during these events or conditions.
471.20 Section 6.3.2.2.7.6 of the SSAR describes the operation of the Automatic Depressurization System (ADS) valves such that the fourth stage valves vent directly into each steam generator compartment on actuation.
Provide the expected frequency at which these valves will open.
Describe the expected cleanup operations that would be expected af ter an inadvertent opening of these valves.
Provide the expected person-Rem a licensee would receive to cleanup after an inadvertent opening of these valves and the length of time it would take to complete the cleanup.