ML19329G320

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Sixty-Day Response to IE Bulletin 80-11
ML19329G320
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/30/1980
From:
BECHTEL GROUP, INC.
To:
Shared Package
ML19329G317 List:
References
IEB-80-11, NUDOCS 8007140428
Download: ML19329G320 (32)
v • d • e


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a G-i SIXTY-DAY RESPONSE TO NRC IE BULLETIN 80-11 DATED MAY 8, 1980 FOR CONSUMERS POWER COMPANY BIG ROCK POINT NUCLEAR PLANT PREPARED BY:

BECHTEL POWER CORPORATION JUNE 30, 1980 a

8007.140MM8 1

BRP Sixty-Day RDepon=3

.NRC IE Bulletin 80-11 Juno 1980 SIXTY-DAY RESPONSE TO NRC IE BULLETIN 80-11 CONTENTS 1.

INTRODUCTION 2.

IDENTIFICATION OF SAFETY-RELATED MASONRY WALLS AND THEIR SYSTEMS A.

Wall' Inspection B.

Wall Plans with Identification Numbers 3.

PRIORITIZED PROGRAM A.

Prioritized Order of Review B.

Completion Schedule 4.

RE-EVALUATION CRITERIA A.

General B.

Analysis C.

Justification of Re-Evaluation Criteria 5.

REFERENCES APPENDIX A.

Wall Plans and Information Tables for Potentially Safety-Related Masonry Walls Figures - Page A-26, Plan Belos Elevation 598' Page A-27, Plan Below Elevation 618' f

i

BRP Sixty-Day Respon=e NRC'IE Bulletin 80-11 June 1980 SIXTY-DA7 RESPONSE TO NRC IE BULLETIN 80-11 1.

INTRODUCTION This report has been prepared in response to NRC IE Bulletin 80-11, dated May 8, 1980.

It has been prepared by Bechtel Power Corporation, Ann Arbor, Michigan, for Consumers Power Company's (CPCo's) Big Rock Point Nuclear Plant.

This report submits information requested in Items 1, 2a, and 3 of NRC IE Bulletin 80-11, dated May 8,1980.

A total of 24 potentially safety-related masonry wall segments have been identified.

A masonry wall may be composed of several segments.

For purposes of identifica;'.on, total count, and re-evaluation, a masonry wall segment has been defined as a uniform, straight run of wall between support or terminal points.

2.

IDENTIFICATION OF SAFETY-RELATED MASONRY WALLS AND THEIR SYSTEMS Safety-related systems, components, and structures have been generally defined as those listed on the Big Rock Point. plant Q list.

The boundaries of seismic analyses performed in the course of responding to NRC IE Bulletin 79-14 have also been used where applicable in the determination of whether an item is safety related.

CPCo has designated potentially safety-related masonry walls at the Big Rock Point plant.

CPCo has also performed a search for potentially safety-related masonry walls in safety-related areas not shown on the design drawings.

l Safety-related systems which are either attached to, penetrate, or are in proximity to potentially safety-related masonry walls are listed in Appendix A.

l For purposes of identification, proximity is defined as within an arc length equal to a masonry wall height from the base of each face of the masonry wall extending to the floor.-

Furthermore, in plan view, proximity is defined by lines normal to the masonry wall extending l

from the ends of the masonry wall.

Proximity does not l

extend beyond compartments.

1

BRP Sixty-Day Rasponse NRC IE Bulletin 80-11 June 1980 The potentially safety-related masonry walls do not generally support a structurally significant amount of equipment.

A.

WALL INSPECTION Identification of potentially safety-related masonry walls started in May 1980.

This included a review of design drawings, the plant Q list, and a walkdown of the plant.

A team started a detailed inspection of.asonry walls on June 23, 1980.

The team is collecting, verifying, and recording information regarding the as-built condition of existing masonry walls and structurally significant attachments.

The presence of safety-related items in proximity to or attached to the masonry walls is also documented.

In some instances, ALARA considerations require that time spent near a masonry wall be minimized and that the inspection he limited to visual observations from some distance away from the masonry wall.

These observations were compared with the design drawings.

Confidence was established that the data obtained are adequate for masonry wall re-evaluation, and it is not intended that a further inspection be made cf these masonry walls.

B.

WALL PLANS WITH IDENTIFICATION NUMBERS Plans have been prepared to locate and number masonry walls (Appendix A).

Only the masonry walls which were l

designated as potentially safety related are further discussed and documented in this report.

3.

PRIORITIZED PROGRAM i

l A.

PRIORITIZED ORDER OF REVIEW Safety-related masonry walls will be re-evaluated using the following order of priority:

1)

Masonry Walls Supporting Safety-Related Equip-ment with Estimated Design Loadings Greater than 100 Pounds, or Safety-Related Piping 2-1/2 Inches in Diameter or Greater l

2)-

Masonry Walls Supporting other Safety-Related Items 3)

Masonry Walls with Safety-Related Equipment in Proximity f-2

BRP Sixty-Day R32pon2@

NRC IE Bulletin 80-11 June 1980 B.

COMPLETION SCHEDULE It is anticipated that the re-evaluation of safety-related masonry walls to acceptance criteria prepared by Bechtel Power Corporation will be completed by November 4, 1980.

4.

RE-EVALUATION CRITERIA A.

GENERAL

)

The Big Rock Point plant Final Hazards Summary Report 1

(FHSR) does not specifically address masonry walls.

Loadings will be defined from the FHSR and existing analyses for Seismic Category I structures.

Load combinations will contain the applicable elements specified in the FHSR.

B.

ANALYSIS Analyses will be performed using standard calculation procedures to determine the structural adequacy of the safety-related masonry walls.

Masonry walls are con-sidered to be isotropic, elastic material.

Plate or beam theory will be used to satisfy static equilibrium under all loading conditions.

Cracked and/or uncracked section analyses will be performed, as applicable, to determine the stresses in the masonry and in the reinforcing steel.

Highly stressed areas will be checked against the corresponding allowable stresses.

C.

JUSTIFICATION OF RE-EVALUATION CRITERIA Justification for the re-evaluation criteria will be submitted with the re-evaluation report within 180 days of the date of the bulletin received.

Justifications will be based on reference to existing codes and estab-lished standards of practice related to concrete and masonry design.

It is anticipated that such justification will be considered appropriate, and that a test program will not be necessary, except as required to determine project unique structural properties and any other properties for which data are not available or cannot otherwise be determined.

5.

REFERENCES NRC IE Bulletin 80-11, dated May 8, 1980 A.

U.S.

B.

Big Rock Point Nuclear Plant, Final Hazards Summary Report, Docket 50-155 l

L l

l 3

f L

BRP Sixty-Day Responsa NRC IE Bul'letin 80-11 Juna 1980 APPENDIX A WALL PLANS AND INFORMATION TABLES FOR POTENTIALLY SAFETY-RELATED MASONRY WALLS The attached identifies safety-related equipment and systems associated with safety-related masonry walls.

This listing is subject to revision.

The listing of systems associated with certain items is intended to reflect the primary system or systems associated with the par-ticular item.

For certain items, especially those associated with walls M100.14 and M100.18, a large list of systems would be required to completely define safety-related equipment in cabinets, conduits, and cable trays.

For this report, the term "various" is used to include reactor cleanup, control rod drive, shutdown cooling, reactor coolant, core spray, emergency core cooling, and/or other systems which have circuitry combined in the con-duits and cable trays noted in the attached tables.

These masonry walls do not generally support a structurally significant amount of nonsafety-related equipment.

Therefore, attached nonsafety-related equipment and systems are not listed.

Attached nonsafety-related equipment will be considered in the re-evaluation of these masonry walls.

The masonry wall number is the drawing number followed by a decimal, followed by the wall number indicated on the drawing.

4 e

l i

s

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A-1

'N N

Appendir. A O

WALL M100.1-Item System Conduit Off-gas monitoring off-gas discharge Off-gas monitoring monitor Instrumentation Off-gas monitoring e

O

\\

A-2

Appendix A WALL M100.2

_ Item System Instrumentation Off gas monitoring 9

e A-3 l

Appgndix A WALL M100.3

Item System Conduit Reactor depressurization system Uninterruptible power Reactor depressurization system supply (UPS) b,attery charger / inverter UPS batteries Reactor depressurization system One-and 2-inch pipe Fire system b

A-4

Appsndix A WALL M100.4 Item System Conduit Reactor depressurization system UPS battery charger /

Reactor depressurization system

~

inverter UPS batteries Reactor depressurization system one-and 2-inch pipe Fire system 6

A-5

AppOndix A WALL M100.5 Item System Six-inch pipe Fire system Conduit Reactor depressuriration system 9

9 A-6

Appandix A WALL M100.6 Item System One-and 2-inch pipe Fire system UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system Conduit Reactor depressurization system A-7

nyyussuax n WALL M100.7 Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries-Reactor depressurization system Conduit Reactor depressurization system one-and 2-inch pipe Fire system O

o l

1 l

L l

l A-8

nweuuta n WALL M100.8 Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system Conduit Reactor depressurization system one-and 2-inch pipe Fire system i

i e

A-9

negacau s s n WALL M100.9 Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system Conduit Reactor depressurization system One-and 2-inch pipe Fire system l

A-10 l

L

App:ndix A WALLM100.b.0, Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system

~

Conduit Reactor depressurization system One-and 2-inch pipe Fire system e

P A-11

..c c -. 0 - - m o.

A WALL M100.11 Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system Conduit' Reactor depressurization system One-and 2-inch pipe Fire system 4

e e

b i

4 1

A-12

. ~. -

Appendix A WALL M100.12

-Item System UPS battery charger /

Reactor depressurization system inverter UPS batteries Reactor depressurization system Conduit Reactor depressurization system One-and 2-inch pipe Fire system 4

S A-13 t

Appandix A WALL M100.13 Item Svstem UPS battery charger /

Reactor depressurizatioa system inverter UPS batteries Reactor depressurization system Conduit Reactor depressurization system One, 2, 3, and Fire system 6-inch pipe e

(

i A-14

I WALL M100.14 Item System Three-and 6-inch pipe Fire system Four-and 6-inch pipe Post-incident cooling Batteries Station power Motor control center Primary coolant system /

125 V de emergency condenser system Conduit Various Cable tray Various 5

I A-15

appanaxx a WALL M100.15 Item System Two, 3, and Fire system 6-inch pipe Conduit Reactor depressurization system G

i I

A-16

AppCndix A WALL M100.16 Item System Rod position MG set Reactor protection system Three-inch pipe

' Fire system Four-and 6-inch pipe Post-incident cooling Conduit Reactor depressurization system /

2,400 V cable Batteries Station power Cable tray Various Battery chargers Station power Ground detector Station power w

A-17

Appanalx A WALL M100.17 Item System Cable tray Reactor depressurization system, 2,400 V Four-and 6-inch pipe Post-incident cooling Conduit Reactor depressurization system Switchgear Reactor feedwater and reactor circulation systems and station power transformers d

6 e

A-18

App;ndix A WALL M100.18 Item System Load center, 480 V Emergency conderser inlet Motor control centers Reactor cleanup, shutdown cooling, lA, 2A, and 2B and containment spray Junction boxes JB42, Emergency core cooling and JB43, and JB44 containment isolation Switchgear Reactor feedwater and reactor circulation systems and station power transformers Conduit Various Cable tray Various O

A-19 4

l nyyuuu n n WALL M100.19 Item System Four-and 6-inch pipe Post-incident cooling Three-inch pipe Fire system Cable tray Various e

6 e

l s

A-20

nyy=cm u a WALL M100.20 Item System One, 2, 3, 4,

Fire system and 6-inch pipe Four-and 6-inch pipe Post-incident cooling Cable tray Various Conduit Systems (2,400 V)

I i

A-21 t

m.

Appandix A WALL M100.21 Item System Two, 4, and 6-inch Fire sys' em pipe and valves Conduit System (2,400 V)

Cable Tray Various O

4 e

1 A-22

Appandix A WALL M101.1 Item System Control panels Reactor depressurization system

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A-23

Appandix A WALL M101.3 Item System Downcomers Primary coolant system e

O A-24

App;ndix A WALL M101.4 Item Sys*.em Heat exchangers Primary coolant system b

O A-25

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