ML19329A189

Forwards Request for Addl Info Re Seismic Qualification of Station Emergency Power Path

ML19329A189
Person / Time
Site:	Oconee
Issue date:	02/10/1977
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
References
NUDOCS 7912300220
Download: ML19329A189 (3)

Text

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FEB 101977 1

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MEMORANDUM FOR K. R. Coller, Assistant Director for Operating Reactors, DDR i

i FRON:

D. C. Eisenhut, Assistant Director for Operational Technology, DOR

SUBJECT:

SEISMIC QUALIFICATION OF OCONEE EMERGENCY POWER PATE l

Plant Name: Oconee N lear Station Units 1, 2 and 3 i

Licensing Stage:, e ng Plants i

Docket Numbers: $0-269 50-270, 50-289 Branch and Projec ger Requesting Assistance ORB 1, J. D. Neighbors l

Description of Request: TAC 6048 - ORB-1-250 Review Status: Awaiting Additional Information The Engineering Branch, Division of Operating Reactors has reviewed the information submitted with the letter dated October 7, 1976.

We find that before we can camplete our review, additional inforination ii as indicated in thajenclosure ;is 'necessary.;;-

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It should be pointed out that our review pertains only to the seismic l

capability of the emergency power path and not to the General Design

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Criterion nu:nber 2 of the Appendix A to the 10 CFR Part 50.

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D. G. Eisenhut, Assistant Director for Operational Technology Division of Operating Reactors I

Enclosure:

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FEB 101977 t

t K.~ R. Goller, Assistant Director for Operating Reactors, D MEMORANDUM FOR:

DOR D. G. Eisenhut, Assistant Director for Operational Technolo FROM:

SEISMIC QUALIFICATION OF OCONEE EMERGE

SUBJECT:

Oconee Nuclear Station Units 1, 2 and 3 Plant Name:

Operating Plants Licensing Stage: 50-269, 50-270, 50-289 GRB 1, J. D. Neigh >rs Docket Numbers:

Branch and Project Manager Requesting Assistance:

TAC 6048 - ORB-1-250 Description of Request: Awaiting Additional Information Review Status:

i ed the The Engineering Branch, Division of Operating Reactors has rev ew 76.

information submitted with the letter dated October 7, 19 ~

f tion We find that before we:canjcomplete our_ review, additional in orma as indicated in the enclosure, is necessary.'

i i It should be pointed out that our review pertains only to the se sm c General De. sign capability of the emergency power path and act to th

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D. G. Eisenhut, Assistant Director for Operational Technology Division of Operating Reactors

Enclosure:

As stated cc:

V. Stello L. Shao W. Butler A. Schwencer D. Neighbors R. Stuart l

P. Atherton 1

K. Jabbour G..Bagchi l

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b OCONEE NUCLEAR STATION UNITS 1, 2 & 3

. SEISMIC CAPABILITY OF EMERGENCY POWER PATH ENGINEERING BRANCH-DIVISION OF OPERATING REACTORS

. REQUEST FOR ADDITIONAL INFORMATION TAC #6048 1.

For each of the structures indicated in Table I describe foundation

condition i.e soil or rock, indicate how soil-structure interaction was accounted for, discuss what precautions were taken to stabilize the fill soil where applicable, provide the input response spectra, indicate the damping values and the extent to which a three directional-earthquake was considered for the design and discuss the load combinations investigated.

2. : Describe the dynamic model of the transmission line and the towers.

j Indicate how the relative displacements of the ground between the towers during a seismic event are accounted for.

Identify the critical sections on the transmission line, the towers and their foundations and provide a' stress summary comparing the stresses against the acceptance. criteria citing the applicable ' codes.-

l 3.

Describe the dynamic model of the 230 kvSwyd Relay House and provide the floor response spectra for different locations at which Category I equipment are supported.

Identify the critical sections and provide a stress summary comparing the stresses against tha acceptance criteria from applicable codes.

4. LProvide the dynamic model of a typical transformer in the overhead emergency' power path including its foundation. Discuss the methods used to seismically qualify the fan coolers mounted on the transformers to ensure operability during and after a seismic event.

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.O-5.. Provide a' copy of a typical equipment procurement specification and discuss the extent and the manner in which the dynamic loads from SSE and OBI,were considered by the supplier to qualify the sub-ject equipment.

6.

On Table 2, identify clearly,for each of the items qualified by a combination of test and analysis, the portions which were qualified Provide by analyses, and the portions which were qualified by tests.

some typical results for the qualification program for the 230 KV Power Circuit Breakers (PCB) and supportive equipment.

7.

For items or portions of items qualified by analysis provide the following information:

State whether the analysis method was static or dynamic, and a.

justify your selection.

b.

Provide a diagram :of ethe math,model. used,for each equipment item.

Provide inpet loads used in the analysis and point of application.

c.

d.

Show location and magnitude of the highest stress intensity and deflection, and list the corresponding margins of safety, Verify that the operability of each equipment item was considered e.

in your analysis and provide a discussion on how the calculated deflections were considered in relation to the operability of the component.

f.

Define the acceptance criteria used in the operability analysis.

8.

in view of the size of the emergency power path, provide a discussion on' detailed inservice inspection and maintenance program to ensure in-tegrity and serviceability of the structures and equipment incorporated j

in the emergency power path. Parameters required to be monitored, for example, may be the tension in overhead cables or deflection of towers.

Indicate your intent to incorporate the proposed inservice inspection and test frequency in the technical specifications of the three nuclear power plants.

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FEB 101977 MEiORANDUM FOR:

K. R. Goller, Assistant Director for Operating Reactors, DOR D. G. Eisenhut, Assistant Director for Operational Technology, DOR FROM:

SUBJECT:

SEISMIC QUALIFICATION OF OCONEE EMERGENCY POWER PATH 3

Plant Name: Oconee Nuclear Station Units 1, 2 and 3 Licensing Stage: Operating Plants Docket Numbers:

50-269, 50-270, 50-289 Branch and Project Manager Requesting Assistance: ORB 1, J. D. Neighbors Description of Request: TAC 6048 - ORB-1-250 i

Review Status: Awaiting Additional Information The Engineering Branch, Division of Operating Reactors has reviewed the information submitted with the letter dated October 7,1976.

We find that'before we can complete our review, additional information as indicated in the enclosure, is necessary.

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It should be' pointed out that our review pertains only to the seismic capability.of the emergency power path and not to the General Design Criterion number 2 of the Appendix A to the 10 CFR Part 50.

h -k I A l.A.

D. G. Eisenhut, Assistant Director for Operational Technology Division of Operating Reactors

Enclosure:

As stated cc:

V. Stello L. Shao W. Butler A. Schwencer

- D. Neighbors R. Stuart P. Atherton K. Jabbour G. Bagchi l

i L_

t OCONEE NUCLEAR STATION UNITS 1, 2 & 3 SEISMIC CAPABILITY OF EMERGENCY POWER PATH ENGINEERING BRANCH-DIVISION OF OPERATING REALTORS REQUEST FOR ADDITIONAL INFORMATION TAC #6048 1.

For each of the structures indicated in Table I describe foundation condition i.e, soil or rock, indicate how soil-structure interaction was accounted for, discuss what precautions were taken to stabilize the. fill-soil where applicable, provide the input response -pectra, indicate the damping values and the extent to which a three directional earthquake was considered for the design and discuss the load combinations investigated.

i 2.

Describe the dynamic model of the transmission line and the towers.

Indicate how the relative displacements of the ground between the

towers'during a seismic event are accounted for.

Identify the critical sections on the transmission line, the towers and their foundations and provide a stress summary comparing the stresses against'the acceptance criteria citing the applicable codes.

Describe the~ dynamic model of the 230 kv5wyd Relay House s.

and provide the floor response spectra for different locations at which Category I equipment are supported.

Identify the critical sections and provide a stress summary comparing the stresses against the acceptance criteria from applicable codes.

4.

Provide the dynamic model of a typical transformer in the overhead emergency power path including its foundation. Discuss the methods used to seismically qualify the fan coolers mounted on the transformers to ensure operability during and after a seismic event.

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Provide a copy of a typical equ'ipment procurement specification and 5.

discuss the extent and the manner in which the dynamic loads from SSE' and OBE were considered by-the supplier to qualify the sub-ject equipment.

n Table 2, identify. clearly,for each of the items qualified by a 6.

e combination of test and analysis, the portions which were qualified Provide by analyses, and the portions which were qualified by tests.

some typical results for the qualification program for the 230 KV Power' Circuit Breakers (PCB) and supportive equipment.

For itemslor portions of items qualified by analysis provide the 7.

following information:

State whether the analysis method was static or dynamic, and a.

justify.your selection, b.

Provide a diagram of the math model used for each equipment item.

Provide input loads used in the analysis and point of application.

c.

I Show location and magnitude of the highest stress intensity and d.

deflection, and list the corresponding margins of safety.

Verify that the operability of each equipment item was considered e.

in your analysis and provide a discussion on how the calculated deflections were considered in relation to the operability of the component.

f.

Define the acceptance criteria used in the operability analysis.

-In view of the size of the emergency power path, provide a discussion 8.

on detailed inservice inspection and maintenance program to' ensure in-tegrity and serviceability of the structures'and equipment incorporated in the emergency power path. Parameters required to be monitored, for example, may be the tension in overhead cables or deflection of towers.

Indicate your intent to incorporate-the proposed inservice inspection and test frequency in the technical specifications of the three nuclear power plants.

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