L-76-184, Letter Transmitting Supplemental Information Related to Proposed Modification of Spent Fuel Storage Facility Originally Submitted on January 28, 1976

Letter Transmitting Supplemental Information Related to Proposed Modification of Spent Fuel Storage Facility Originally Submitted on January 28, 1976

ML18227D132
Person / Time
Site:	Turkey Point
Issue date:	05/10/1976
From:	De Mastry J, Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-76-184
Download: ML18227D132 (11)

Text

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-4 Ql lgr' FLORIDA POWER 5 LIGHT COMPANY L-76-184 May 10, 1976 C??

Office of Nuclear Reactor Regulation Attn: Mr. Victor Stello, Jr., Director

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Division of Operating Reactors U. S. Nuclear Regulatory. Commission Washington, D. C. 20555

Dear Mr. Stello:

Re Turkey Point Plant Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility Operating Licenses DPR-31 and DPR-32 Supplemental lnformation Attached herewith is supplemental information related to our pioposed modification of our spent fuel storage facility originally submitted on January 28, 1976.

This information is submitted as revision 2 of our Spent Fuel Storage Facility Modification Safety Analysis Report.

Very truly yours, g:4i l-( /jV~

b?p~~'Robert 000ssfs0 E. Uhrig y pgg Vice President 9

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cc: Jack R. Newman, Esp.

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2. The loads from paragraphs 1, 2a and 2d and a maximum earthquake(E')

acting simultaneously.

3. The loads from paragraph 5.

(Note that the design basis which ensures maintenance of structural integrity during and after the maximum earthquake (E') does not permit significant yielding. The design earthquake (E) which is a factor of 0.5 or more, less than E', is not as restrictive compared with the upset allowable stress limits in Table 3.2-2, and is, therefore, not considered.)

The heat load in the pool resulting from the addition, of long-decayed fuel will not appreciably change from that of the original design con-dition. The spent fuel pit walls, as stated in the PSAR section 5.2.3 are designed to withstand thermal stresses associated with a thermal gradient of 150'lT (between inside and outside of pool). This was the most severe condition considered in the design.

The maximum uplift load available from the fuel handling crane is a less severe loading on the fuel rack structure than that resulting from the maximum earthquake (E').

Structural design precludes placing a fuel assembly between cells, and the rack will withstand the loadings imposed by a postulated dropped fuel assembly.

Reference:

Section 3.2 (1) Gabrielson,. V. K., "SHOCK A Computer Code for Solving Lumped-Mass Dynamic Systems SCL-DR-65-34," January, 1966 Rev 1 4/30/76 Rev 2 5/10/76

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Regulatory Guide 1.29 states "The pertinent Quality Assurance require-ments of Appendix B to 10 CFR 50 should be applied to all activities affecting the safety related function ...

Combustion Engineering fully complies in all respects with the pertinent requirements of Appendix B 10'CFR 50 for the design, procurement, and 2 fabrication of the spent fuel racks. bQC 5.1 Rev. 1, Class 2A and the Engineering Specification address the pertinent, applicable portions of 1 10 CFR 50 Appendix B to cover the fabrication of the spent fuel'acks The following tabulation indicates the controlling documents which meet the pertinent Appendix B 10. CFR 50 requirements fox the design and procurement phase (Mindsor column) and the fabrication phase (Fabricator column).

Fabricator Criterion Windsor (Su lier)

CE Power Systems MQC 5.1 QA Manual II III N/A IV MQC S.l V

VI VII VIII N/A WQC 5.1 6 CE Eng. Spec.

IX CE Power Systems QA Manual X

XI N/A XII ll MQC 5.1 XIII CE Power Systems QA Manual MQC 5.1 & CE Eng. Spec.

XIV XV XVI XVII XVIII The spent fuel racks are manufactured from the following material:

ASTM-A-240 (sheet and plate stock), ASTM-A-276 (Bar Stock), AMS-E-308-15 (Meld Mire), and AMS E-308-16 (Meld Mire).

I ANSI 45.2.5 "Supplementary Quality Assurance Requirements for Install-ation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants" is not considered applicable to the design, procurement and shop fabrication of the spent fuel racks, since the standard is directed at site-related activities. However, the qualification of welders and welding proce-dures for the shop fabrication of these spent fuel racks is in accord-ance with the ASME Section IX requirements which is acceptable under ANSI 45.2.5.

Rev. 1 4/30/76 Rev. 2 '/10/76

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uestion 2(b) Assume that the lower load block of the main crane hook, which is not carrying any load, "two blocks" as it passes over the stored spent fuel; i.e., the crane up-limit switch fails such that the two blocks come together and the cable is broken. Please provide an analysis which demonstrates that the resulting radiological release will be within acceptable limits should the hook and the lower load block fall into'the pool or describe how the hook and lower load block will be prevented from falling into the pool should "two blocking" and a broken cable occur.

~Ras ense: This is provided in revised Section 5.5.

uestion 3 Regulatory Guide 1.29, Seismic Design Classification, states the spent fuel pool structure including the fuel rack should be in accordance with Appendix B 10. CFR 50 Quality Assurance Criteria for Nuclear Power Plan'ts and Fuel Reprocessing Plant. Section 3.6 of your proposal indicates the racks will be manufactured in accordance with the requirements of CE Quality Class 28 as defined in CE specification 00000-HQC 5.1, Vendor Quality Control Program Specifications for CE Quality Class 2. Identify, describe, and justify all deviations and exceptions your referenced quality controls have taken to Appendix B of 10 CFR 50.

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~Res onse: . This is provided in revised Section 3.6.

uestion 4 In ref erence to the spent fuel pool pro j ected decay heat load resulting from the 621 spent fuel assemblies, de-scribe and discuss what assumptions have: been made to get the burnup of the stored fuel. Further identify and discuss the significance of any differences between assumptions made in this proposal and those made in the FSAR.

~Res onse: This is provided in revised Section 4.1.

uestion 5 Assume that the number. of spent fuel assemblies stored in the spent fuel storage pool is about four hundred and that at the next refueling period; the entire core must be removed to accomplish repairs inside the pressure vessel. Under the above assumption, please provide the following information in tabular form:

Rev. 1 4/30/76 Rev. 2 5/10/76 The remaining modules (if any) will be installed with the Unit 4 pit flooded and containing spent fuel. As noted in Section 7.1, administrative procedures will be employed to restrict the movement of the new modules over the stored spent fuel to preclude unacceptable construction incidents.- This installation program will continue throughout the Spxing and Summer of 1977. Fuel will not be stored in the new CE racks without'rior Commission approval.

At the appropriate time in 1977, spent fuel will be transferred from Unit 3 to Unit 4, and the same liner repairs program repeated. A schedule for these activities is shown in Figure 7.2-1.

s uestion 16 Provide sketches of the fuel pool storage racks which define the primary stx'uctural aspects and elements re-lied upon for the structuxe to perform its safety func-tion. Include typical details of all interfaces. with the pool boundaries and connections between modulus.

Also provide sketches of the fuel stoxage pool sho'wing its principal dimensions and structural features and its relationship with surrounding structures and the supporting media.

~Res onse: Rack details will be provided by Hay 19, 1976.

'iguras 3.1-3, 3.1-4, and 3.1-5 show the spent fuel pool principle dimensions and structural features and its relationship with the surrounding structures'and supporting media. General arrangements of the plant at grade eleva-tion 18' 0" is shown in the FSAR Figure 1.2-3.

Provide a list of all design codes, standards, specifi-cations, regulatory guides, and other standards which will be used in the design, fabrication, construction, and inspection of the fuel pool racks.

~Res onse: This is provided in revised Section 3.1.

Rev. 1 4/30/76 Rev. 2 5/10/76 C

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uestion 18 Provide more specific information on the loads, load combinations and acceptance criteria which will be

, utilized in the design of the racks. The staff position-concerning this matter is indicated in 3.8.4-II.3 and 5 of the Standard Review Plan. Inden-tify the magnitude of-all loads considered in the design.

~Res onse: This is provided in revised Section 3.2 and in Table 3e 2 2 ~

uestion 19 Describe the design and analysis procedures for the fuel storage rack, including the expected behavior under load and the mechanism of load transfer to the foundation. Computer programs should be referenced to permit identification with available published programs.

~RSs onse: This will be provided by May 19, 1976.

uestion 20 Identify all the materials and the QA/QC program to be followed for the procurement, fabrication, and construction of the fuel pool racks. Describe the extent to which you intend to comply with ANSI N45.2.5, "Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structure Steel During the Construction Phase of Nuclear Power Plants."

~Res onse: This is provided in revised Section 3.6.

uestion 21 Indicate whether ground response spectra, appropriate damping values, and combination of modes and spatial excitation will be in accordance with Regulatory Guides 1.60, 1.61 and 1.92 respectively for the analysis of the fuel pool and the fuel storage rack seismic system.

~Res onse: This is provided in revised Section 3.2.

uestion 22 Provide sketches of the mathematical model of the fuel pool, fuel storage rack and fuel assembly system which will be used in the analysis. Illustrate on the sketches the mechanism of shear and load transfer to the fuel pool walls'nd foundation slab. Discuss the effects of sloshing water and possible impact of the fuel assem-blies with the rack.

Rev 1 4/30/76 Rev 2 5/10/76

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