ML20149H872

Forwards Request for Addl Info Re Application for Amend to License SNM-1773 Re Storage of Oconee Spent Fuel at McGuire Facility.Response Requested within 30 Days of Receipt of Ltr

ML20149H872
Person / Time
Site:	07002623
Issue date:	07/21/1978
From:	Starostecki R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Parker W DUKE POWER CO.
References
TAC-57316, NUDOCS 8802220157
Download: ML20149H872 (4)

Text

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Docket flo. 70-2623 PDR feiSS:R/F LPDR. Charlotte, FCRR:R/F NC Dcchet l'o. 70-2623 JBMartin LPDR.Walhalla,'

RWStarostecki S.C.

JPRoberts RRentschler JShafer RSkelton IRRirkel LGordon Mr. Williant D. Parker . SKeblusek DVanNiel Vice President NKetzlach BSpitalny Steam Production Departrent (/,/jmys -7/y Pouer Building 422 South Church Street Charlotte, North Carolina 28242

Dear ifr. Parker:

In conducting our review of your application for amen 6:ent to license SNM-1773, dated March 9.1978, relating to the storage of Oconee

' Nuclear Station spent fuel at the ficGuire Nuclear Station, we have determined that we will need the additional infonaation identified in the enclosure to continue our reviews. This request is related to both your safety and enviroinental recorts.

In order for us to rnaintain our review schedule, which is consistent with your needs identified in your letter of liarch 9,1978, your response is requested within thirty (30) days of receipt of this letter.

Please contact us if you have any quertions concerning this request.

Sincerely,

.t

. . . . . m u.w Richard H. Starostechi, Chief Fuel Reprocessing & Recycle Branch Division of Fuel Cycle ?. Paterial Safety

Enclosure:

Request for aiditional infornation 8802220157 780721 PDR ADOCK 07002623 C PDR

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REQUEST FOR ADDITIONAL INFOR'iATI0tl McGUIRE NUCLEAR STATI0tlS UNIT-1

!ection 6.0, Phusical Description of Fuel Handling & Storage Systems i

1. The minimum center-to-center spacing between fuel assemblies in the storage racks should be specified. Consideration should be given to the closest possible position between adjacent assemblies in the racks.

I 2. The following information associated with the fuel assemblies is i required:

a) The naximum U-235 enrichment.

! b) The minimum distance from the top of the fuel section to l the top of an assembly.

c) The minimum distance from the bottom of the fuel section to the bottom of an assembly.

3. In the evaluation of the nuclear criticality safety of the storage array, consideration should be given to the accidental insertion of a fuel assembly between the racks and the nearest concrete wall in the determination of the most reactive configuration.

4. Confirm the rack cross section is 15.5" x 15.5".

5. The minimum qualifications for the reactor engineer (see Q 010.24 in the McGuire FSAR) should be specified.

Section 10.0, Corporate & Station Organization

6. The functions, responsibilities and authorities of the reactor engir.eer should be included.

Section 12.0, Emergency Planniig '

7. Appendix A to Regulatory Guide 3.24 lists the minimum requirements for licensee's plans for coping with radiation emergencies. The folicwir.g items,as listed in Appendix A, were not addressed in your emergency plan.

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Item 2 - A list of persons, other than employees, whose assistance may be needed. This list along with the list of employees who have any special qualifications shall be readily available to the individuals responsible for directing the action necessary to cope with the emergency. Additionally, emergency plan sections 4.4 and 9.1 should be referenced.

Item 4(iii) - Securing the accident area from inadvertent or unauthorized reentry.

Item 7(i) - Identification of individuals directly involved in the accident.

Item 11 - Performance criteria of the various types of emergency equipment.

l Identify the method Duke Power Ccmpany is employing to conform to I

the ab,ove criteria.

8. Tectie. 1? M of the application references Energency Plan Section 5.4.4 as the applicable section to Regulatory Guide 3.24, Item (10). In accordance with the latest version of the emergency plan in possession of this office (A~endment 30 -

Revisicn ll, dated 2/9/76), Section 5.4.4 does not exist.

Section 5.5.4 fits the description of this item. Confirm that this is/is not a typographical error.

9. The shift supervisor is responsible for initiating the Emergency Plan in the case of a warranting situation. Confirm that a shift supervisor will be on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, 7 days a week, beginning at the time spent fuel is received on site, and prior to receipt of an operating license.

10. Have all procedures to enable implementation of the Emergency Plan been written? Have considerations been given for a procedure to notify the remaining construct'en workers in the event of an accident? State the date with respect to receipt of spent fuel at which full implementation of ti e Emergency Plan is in effect.

Section 13.0, Quality Assurance

11. Identify those safety related activities associated with the storage of fuel. State that the safety related functions / activities associated with storage of fuel at ticGuire are covered by "Topical Report, Quality Assurance Program, Duke-l ." -

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12. Will the same quality assurance organizational structure described for use in operating a power plant be applied to storage of fuel only? If not, provide both organizational charts and a description of the cannitted organization to be used prior to operating the plant.

Section 14.0, Station Procedures

13. The review and approval procedures (see section 13.4 in the McGuire FSAR) for fuel handling operations and their audit requirements should be specified.

Section 17.0, Physical Protection

14. As per NRC staff member Robert L. Baer's letter dated June 29, 1978 [

with respect to the review schedule for the Industrial Security Plan, I we understand that a revised security plan will be submitted under Docket 50-369 and 50-370 on July 26, 1978. This plan should i comply with requirements of 573.55 of 10 CFR Part 73. Evaluate this i plan for conformance to the requirements of both 1573.40 and 73.50.

l This plan should be supplied with your application to amend SNM-1773 Reference the applicable sections and add additional paragraphs as necessary for unique 5573.40 and 73.50 requirements. _

Environmental Considerations

15. North Mecklenburg High Schcol, 0.5 miles from the transportation route, population 1600, and Hoechst Fibers, 0.25 miles from the transportation route with 2770 employees, were ured as representative pcpulation centers along the shipping route. Please verify that these tre the best selections and recommend any other schools, factcries, hospitals or other pcpulation centers which may result in higher exposures, if a significant transportation accident would occur near their location.

16. As a part of NRC-Duke discussions which took place June 2, 1978 on spent fuel cooling requirements, Duke Power calculated time, exposure and cost considerations for 120 day and 365 day fuel cooling times. '

Inclusion of a fourth case,as presented in the summary of case studies,similar to case one except all fuel transferred is cooled for 270 days or longer would be useful.

17. If cooling water in the spent fuel shipping cask were Icst during transit, what is the maximum expected fuel cladding temperature that would result if the contained fuel had been renoved frcm the Oconee reactor for 120 days, 270 days and 365 days?

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