ML18044A341

Submits Response to NRC 791029 Request for Addl Info Re SEP Structural Topic III-2,Topic III-7.B.1,Topic III-7.B.2, Topic III-7.B.3,Topic III-7.B.4,Topic III-7.B.5, Topic III-7.C & Topic III-7.D

ML18044A341
Person / Time
Site:	Palisades
Issue date:	12/14/1979
From:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Ziemann D Office of Nuclear Reactor Regulation
Shared Package
ML18044A342	List: ML18044A341 ML18044A343 ML18044A344
References
TASK-03-02, TASK-03-07.B, TASK-03-07.C, TASK-03-07.D, TASK-3-7.B, TASK-3-7.C, TASK-RR NUDOCS 7912190466
Download: ML18044A341 (3)

Text

consumers Power

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company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 .* Area Code 517 788-0550 December 14, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2.

US Nuclear Regulatory Commi:,,;sion-Washington, DC 20555 D()CKET 50-255 - LICENSE DPR-20 **

PALISADES. PLANT - ADDITIONAL*.

INFORl't<\TION FOR SEP STRUCTURAL.TOPICS 60nsi.uners fc..wer Company was ::::equested to provide additional inforra2.tion con-:erning S.EP Structural Topi*cs foe the Palisades Plant by NRC letter dated

• October 29, 1979. The foll9~ing ~resents the r~sponses ta those requests:

Topic III Wind and Tornado Loads For ~ach safety-related sr.ructure, describe the procedures tp transfer tornado

.data into design pressure.

Response to Topic III-2 The procedure used to transfet tornado.~ata into design pressure .is located in Pdlisades FSAi.1l Appen.dix A, Section A. 2. c. ASCE Paper Nwnber 3.269 is required ta obtai!l the full procedure.

Section 5. 1. 3. 2. b of tJ:ie f$AR al3o cont.a ins information related to this topic_

Topic III-7.B.l - D~sign Codes, Design Criteria and Load Combinations With regard. to the design of the prestressed concrete containment, provide the design specification and any design rep1.n:ts. This informatii:m should incluqe those requested ir!* Items'.?. through*S*below.

Respon$e td III-7.B.l This information is included in *Items " t.hrough 5 below.*

• 'Z '9 121 9 0 ~ ' ' "

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• Topic III-7.B.2 List the codes and standards (include edition date) used for design and construction of steel members of each safety-related structure.

Response to III-7.B.2 The code and standards used the design and construction of these steel members for each safety-related structure are found in the Palisades FSAR Sections 5. 1. 2, 5. 1. 7_, 5. 2. 2, 5. 3 and Appendi~ B.

Topic III-7 .B.3 List all loads considered in the design of safety-related structures including any missile or pipe break effects.

Response to Topic III-7.B.3 The loads considered in the design of safety-related structures including miss.ile or pipe break effects are listed in the Palisades FSAR Section 5.1.2, 5.1.3, 5.2.1, 5.3, Appendices A and Band Amendment 14, Question 5.11.

Topic III-7.B.4 Provide the design and/or actual material properties (fg and fi) used for steel and concrete elements. For concrete, also provide the age specified and any admixtures used.

Response to Topic III-7.B.4 The design and/or actual material properties use'd for steel and concrete elements are found in the Palisades FSAR Section 5.1.2, 5.1.7, Appendices B and F and Amendment 15, Question 5.28.

Topic III-7 .B.5 P"rovide representative stress* levels (comp_ression, ten:sion and shear) at critical location of each safety-related structure (eg, base of containment internal structures) for each of the load combinations considered in the design.

Response to Topic III-7.B.5 Stress levels at critical location of each safety-related structure are found in the Palisades FSAR Table 5.1 and Figures 5.9 through 5.13.

Topic III-7.C - Delamination of Prestressed Concrete Containment Structures Describ'e the construction procedures for the prestressed containment shell including the tendon tensioning sequence. Provide any inspection reports for

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• the containment that may have assessed the likelihood of delamination occurring in the shell wall or dome. If such inspections were made but not documented, describe the results of these inspections.

Response to Topic III-7.C The procedures for the prestressed containment shell are found in Palisades FSAR Section 5.1.7 and Amendment 14, Questions 5.29 and 5.39.

Topic III-7.D - Containment Structural Integrity Tests Provide any reports that describe the procedures and results of the containment structural integrity test.

Response to Topic III-7.D The structural integrity test report is attached. For additional information, also see Palisades FSAR Section 5.18.

In a telephone conversation on December 10, 1979, Henry Lee (NRC) requested responses to the following additional questions:

Item A Does the code used for construction require consideration of wind and tornado loading for Seismic I?

Response to Item A Yes, the code used for construction requires consideration of wind and tornado loading for Seismic I.

Item B Can we quantify the amount by which seismic stresses exceed wind ~nd tornado loads?

Response to Item B Yes, but this information is not readily available and is not easily acquired.

David P Hoffman Nuclear Licensing Administrator Attachment - Containment Building Structural Integrity Test