ML20151Y094

Forwards BNL Draft Proprietary Rept, Independent Assessment of Severe Accident Risks for Westinghouse Advanced PWR Design (SP/90) Re Review of Module 16, Probabilistic Safety Study of RESAR SP/90.Encl Withheld (Ref 10CFR2.740)

ML20151Y094
Person / Time
Site:	05000601
Issue date:	03/28/1988
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
Shared Package
ML19302D542	List: ML20151Y094
References
NUDOCS 8805040336
Download: ML20151Y094 (3)

Text

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Docket No. 50-601 Mr. W.J. Johnson, Manager Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburg, Pennsylvania 15230

SUBJECT:

REPORT REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of your application for a Preliminary Design r Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16, "Probabilistic Safety Study." As part of this effort, BNL has prepared the attached report on the "back end" of the PRA, entitled "An Independent Assessment of Severe Accident Risks For the Westinghouse Advanced Pressurized Water Reactor Design (SP/90)." We are providing this report to assist you in '

understanding the concerns of the staff and our contractor.

Note that this report documents the results of BNL's review to date. It is anticipated that the review process will not be complete until staff and Westinghouse comments and additional information are evaluated and reviewed by BNL.

The material contained in this enclosure is considered to be proprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740. If you have any questions concerning this matter, please contact me at (301) 492-1120.

. Sincerely, .

1 Thomas J. Xenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects  :

Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page.

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• March 28, 1988 Docket No. 50-601 Mr. W.J. Johnson, Manager Nuclect Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburg, Pennsylvania 15230

SUBJECT:

REPORT REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of your application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16 "Probabilistic Safety Study." As part of this effort, BNL has prepared tho attached report on the "back end" of the PRA, entitled "An Independent Assessment of Severe Accident Risks For the Westinghouse Advanced Pressurized Water Reactor Design (SP/90)." We are providing this report to assir.t you in understanding the concerns of the staff and our contractor.

Note that this report documents the results of BNL's review to date. It is

, anticipated that the review process will not be complete until staff and Westinghouse comments and additional information are evaluated and reviewed by BNL.

The material contained in this enclosure is considered to be proprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740. If you have any questions concerning this matter, please contact me at (301) 492-1120. I Sincerely, p ._

Thomas J. Xen . ,Projec anager Standardization and Non- ower Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation  !

Enclosure:

As stated i cc: See next page.

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-Docket No. STN 50-601 RESAR-SP/90 cc: l Trevor Pratt Brookhaven National Laboratory Building 130 Upton, New York 11973 Mr. William Schivley Westinghouse Electric Corporation ,

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Mail Stop 4-08 Box 355 Pitthburgh, Pennsylvania 15230 L

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NUCLEAR REGilLA MRY COMMISSION 10 CFR Part 31 1

Order Modifying General License Issued Pursuant ,

to 10 CFR Section 31.5 Agency: Ne: lear Regulatory Comission Action: Order Modifying General License  !

Sumary: The general license in 10 CFR 31.5 is being modified imediately ,

effective with respect to the use of all polonium-210 static elimination devices distributed by Minnesota Mining and Manufacturing Company (3M). General licensees in possession of such devices are ordered to suspend use and return.

them to 3M in accordance with a prescribed schedule. The modification order will remain in effect until further notice by the Comission, j

9 For Further Informaticn

Contact:

Operations Center, U.S. Nuclear Regulatory Comission, area code 202-951-0550 (open 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day).

Order Modifying General License a

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Minnesota Mining and Manufacturing Company (3M or Licensee) is the holder of l l t 4

byproduct material licenses issued by the Nuclear Regulatory Corrmission (the f Comission or NRC) pursuant to 10 CFR Part 30. License No. 22-00057-06 >

authorizes the Licensee to use a variety of radionuclides, including l polonium-210 (Po-210), and to conduct a variet) of activities with these materials including manuf acturing, testing, installire and repairing radioactive souren ; and th Q vices in which they are used.

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License No. 22-00057-32G, issued pursuant to 10 CFR Parts 30 and 32, authorizes the Licensee to distribute Po-210 sources for use in static elimiration devices to persons generally licensed in accordance with the provisions of;10 CFR 31.5.

II On January 25,1988, these 3M licenses were amenced by an imediately effective Order which, among other things, suspended the authority of 3M to distribute Model Nos. 902, 902F, 906, and 908 Po-210 static elimination devices.

Subsequent to issuing the January 25, 1988 Order, th( NRC received a list from 3M of general licensees who possess the above-described static elimination devices. Included in the list were general licensees which appeared to be manufacturing products or packages for products such as food, ,

i beverages, pharmaceuticals and cosmetics which are to be consumed by or applied to humans. NRC inspectors roviewing records during the week of January 24, 1988 et the 3M Center in St. Paul, Minnesota also detennineo that there were indications of a number of failed devices during the previous year that

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I included devices used at facilities which menufacture products for human j consumption. Further investigation at general licensee facilities conducted by l

3M, NRC and State personnel revealed additional instances of device failure including some located at beverage and food processing plants.

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s On February 5,1988, 3M issued a letter to all of its customers using the above-specified models of the device, directing such users to remove the devices from applications related to the packaging of food, beverages, pharmeeuticals, or cosmetics and to return them to 3M. 3M's action was confirmed by Order dated February 5,1988. The February 5,1988 Confirmatory Order modified 3M's License to require 3M to inform all users of its Model 902, 902F, 906, and 908 static eliminators involved in the packaging of food, beverages, pharmaceuticals and cosmetics that it was withdrawing these devices from service and that such devices were to be returned to 3M.

Subsequent to issuing the February 5,1988 Confirmatory Order, the NRC received reports of additional failed devices. Some of the newly reported failures involve model numbers not specified in the January 25, 1988 Order. For example, Model No. 907 static elimination devices, which utilize blown rather than compressed air, have been found leaking in at least 3 cases. In addition, bar-type s+: tic elimination devices, specifically Model No. 210, have been reported to have leaked. Some of these blown-air and bar-type devices are used in plants that manufem.e products and packages, or package materials for  :

4 products, which would constitute a direct pathway for human exposure if contaminated.

, On February 8,1988, 3M submitted a brief report of its work under the Order l of January 25. The NRC met with 3M at Region III offices on February 11, 1988, to discuss these results and to hear of 3M's proposed plan of action.

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Based on information reviewed to date, static eliminators have experienced frequent failures in what appear to be normal and customary industrial d

environments (i.e., under ordinary conditions of use). Such failures are in direct conflict with the licensing basis of these devices including the i requirements of 10 CFP. Section 32.51(a)(2)(1) which states, in part, that

"[u]nder ordinary conditions of handling, storage and use of the device, the byproduct material contained in the device will not be released . . . ."

On February 12,1988, the 3M licenses were further amended by an immediately

effective Order which, among other things, suspended the authority of 3M to

! distribute any Po-210 static elimination devices involved in the production or j packaging of food, beverages, pharmaceuticals, or cosmetics, and required 3M to recall these devices by March 2, 1988.

Subsequent to issuing the February 12, 1988 Order, the NRC has continued to i receive reports of additioral failed oevices. Some of the newly reported l l

l failures are located in high public access areas such as shopping malls, i Based on the information presented above, the NRC ro longer has confidence that the licensing basis of Po-210 static elimination devices authorized for 1

distribution to general licensees by License No. 22-C0057-32G meets the '

requirements of 10 CFR Section 32.51. Accordingly, the Commission finds that the public health, safety, and interest require that the actions specified in i

Section !!I of this Order be made effective imnediately, j r

s.

The NRC has been informed that some of these Po-210 static eliminators are used .

1 in industrial or commercial service where suppression of static electricity is needed for workplace safety where significant fire, explosion or other hazards might otherwise exist.

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Therefore, in exercising the necessary radiological i

safety precaution of removing these devices front use, the NRC recognizes the .

need to consider the possibility of at least temperarily approving continued use where competing safety risks are involved and process surveillance is sufficient.

, III 1

1 Accordingly, pursuant to Section 01, 161b, and 1611 of the Atomic Energy Act

of 1954, as anended, and 10 CFR 2.204 ano Parts 30 ard 31 of the Commission's 1 regulatiens, IT IS HEREBY ORDERED, EFFECTIVE IMMEDIATELY, THAT

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A.

1 The general license in 10 CFR 31.5 is suspended irmediately with respect to the use of any Po-210 static elimination device manufactured by 3M I and distributed to general licensees pursuant to 3P License Nos, i

22-00057-06 and 22-00057-32G, except as provideo in Paragraph C. below. l 1

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8. The general license in 10 CFR 31.5 is further tredified to require general licensees possessing the static elimination devices described in Paragraph A. above to return them, within 90 days of the date of this Order to 3M in accordance with instructions provided by 3M, except as provided in Paragraph C. below,

t. If a general licensee determines that use of 3M static elimination devices is essential for safety, the general licensee may seek prior written approval from the appropriate NRC Regional Administrator or Agreerent State for temporary continued use under surveillance to be specified.

Oral requests for approval must be confirmed in writing. This provision does not apply to use of the devices in the production or packaging of food, beverages, pharmaceuticals, medical devices, or cosmetics.

The Director, Office of Nuclear Material Safety and Safeguards, may in writing relax or rescind any of the above conditions for good cause shown by the licensee.

IV Pursuant to the Atomic Energy Act of 1954, as amended, a general licensee subject to this Orcer or any other person adversely affected by this Order nay request a hearing within 30 dcys of the date of this Order. Any request for a hearing shall be subtritted to the Director, Office of Nuclear Material i

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Safety and Safeguards, U.S. Nuclear Regulatory Congnission, Washington, D.C.

20555, with a copy to the Assistant General Counsel for Enforcenent at the same address. If a person other than a general licensee requests a hearing, that person shall set forth with particularity in accordance with 10 CFR Section 2.714 the manner in which the person's interest is adversely affected by this Order. A request for a hearing shall not stay the imediate effectiveness of this Order.

If a hearing is requested by a general licensee or a person whose interest is adversely affected, the Conraission shall issue an Order designating the time and place of any hearing. If a hearing is ha10, the issue to be considered at i such hearing is whether this Order should be sustained.

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FOR THE NUCLEAR REGULATORY COMMISSION l

/ :_ _ w Robert M. Bernero, Deputy Director Office of Nuclear Material Safety i

1 and Safeguarcs Dated at Rockville, Maryland this 18th day of February,1988

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