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Forwards Response to IE Bulletin 80-11, Masonry Wall Design & Phase 3 Submittal Delineating Results of re-evaluation of safety-related Concrete Masonry Walls.Rept Suppls 800711 & 1111 Ltrs
	ML20010F797
Person / Time
Site:	Crane
Issue date:	08/31/1981
From:	Hukill H; Metropolitan Edison Co
To:	Grier B; NRC Office of Inspection & Enforcement (IE Region I)
References
	IEB-80-11, L1L-185, LIL-185, NUDOCS 8109110349
	Download: ML20010F797 (66)
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Metropolitan Edison Company N

Post Office Box 480 Middletown, Pennsylvania 17057 Writer's Direct Dial Number August 31, 1981 LlL-185 k

Office of Inspection and Enforcement p

Attn:

B.11. Grier, Director U. S. Nuclear Regulatory Commission 631 Park Avenue S{p 10198;5 -

King of Prussia, PA 19406 nW%,

y)

Dear Sir:

~

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating Licensing No. DPR-50 Docket No. 50-289 IE Bulletin 80-11 Enclosed please find the response to the items of the subjact bulletin (enclosed) and t-he phase 3 submittal delineating the results of the re-evaluation of Safety-Related Corcrete Masonry Walls (enclosed). This report is submitted in accordan e with the requirements as set forth in the subject hulletin, and is to supplement our letters of July 11, '.980 (TLL330) and November 11, 1980 (TLL584). This report indicates that l

all of the block walls analyzed are qualified contingent upon the nec-essary repair work. Walls affecting the operability of safety related equipment will be repaired prior to restart as discussed in the response to item 1 of enclosure.

Sincerely, a

11. D.

kill l

Director, TMI-l l

HDil: CJS : mar l

Enclost.res cc:

L. Barrett w/o Enclosures D. Dilanni w/o Enclosures

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11. Silver w/o Enclosures bI l V. Stello w Enclosures J. F. Stolz w Enclosures 0109110349 810831

{'DR ADOCK 05000289 PDR 1

Metropohtan Ed. son Company is a Member of the General Pubhc Utihties System

METEOPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 This letter is submitted in support of the Nuc1 car Regulatory Commission request concerning the May 8, 1980 letter transmitting IE Bulletin 80-11.

All statements contained in these responses have been reviewed and all such statements made and matter set forth therein are true and correct to the best of my knowledge, information and belief.

T

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By th v

i Vice President 5W Sworn and subscribed to me this 3 I dayofOn/%lLCL,F 1981.

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By a

Notahyhublic Psuf1A MY LUBRrCHT; NMary Pahlic kW4' W

'Juphin C%nty:

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% CctrJawoo Empires A.ust 4 '983 1

2 Response to IE Bulletin 80-11 Item 1.

Identify all masonry walls in your facility which are in proximity to or have attachments from safety-related piping or equipment such that wall failure could affect a safety-related system.

Des-cribe the systems and equipment, both safety and non-safety-related, associated with these masonry walls.

Include in your review, masonry walls that are intended to resist impact or pressurization loads, such as missiles, pipe whip, pipe break, jet impingement, or tornado, and fire or water barriers, or shield walls.

Equipment to be considered as attachments or in proximity to the walls shall in-clude, but is not limited to, pumps, valves, motors, heat exchangers, cable trays, cable / conduit, HVAC ductwork, and electrical cabinets, instrumentation and controls. Plant surveys, if necessary for arean inaccessible during normal plant operation shall be performed at the earliest opportunity.

Response a) The following masonry block walls were determined to have safety equipment on or in proximity to them:

Auxiliary Building Walls Other Wal]s AB-2, A3-3, AB-4 RB-1 AB-6. AB-7, AB-8, AB-9 AB-10, AB-11,AB-12, AB-13 See attachment 1 of July 11, 1980 for further details.

These walls will be repaired prior to restart.

b) Additionally the following masonry block walls have not been comp-letey evaluated but will be repaired prior to restart.

Auxiliary Building Walls AB-1 and AB-5 c) Furthermore, AB-14 is located in a high radiation and contaminated area and has not been evaluated.

d) TB-1 was reevaluated and it was determined that no safety-related equipment is on or in 1coximity to this wall.

e) FEB 1 and 2 were evaluated in the November 11, 1980 submittal and determined that no safety-related equipment was on or in close proximity to the wall, f) For further details see attachments 1 and 2 of the July 11, 1980 submittal and attached Topical R2 port paragraphs 1 and 2.

A

Item 2.

Provide a re-evaluation of the design adequacy of the walls identified in It.cm 1 above to determine whether the masonry walls will perform their intended function under all postulated loads and load combinations.

In this regard, the NRC encourages the formation of an owners' group to establish both appropriate re-evaluation criteria and where necessary, a later confirmatory masonry test proFram to quantify the safety margins established by the re-evaluation criteric (this is discussed further in Item 3 below).

Response

See attached Topical Report paragraph 4 and enclosure 2 of the November 11, 1980 submittal.

Item 2a.

Establish a prioritized program for the re-evaluation of the masonry walls. Provide a description of the program and a de-tailed schedule for completion of the re-evaluation for the categories in the program. The completion date of all re-evalua-tions should noc be more than 180 days from the date of this Bulletin.

A higher priority should be placed on the wall re-evaluations considering safety-related piping 2-1/2 inches or greater in diameter, piping with support loads due to thermal expansion greater than 100 pounds, safety-related equipment weighing 100 pounds or greater the safety significance of the potentially affected systems, the overall loads on th' wall, and the opportunity for performing plant surveys and, if <ecessary, modifications in areas otherwise inaccessible.

The factors described above are meant to provide guidancc in determining what loads may signficantly affect the masonry wall analyses.

Response

See attachments 2 and 4 of the July 11, 1980 submittal.

Item 2b.

Submit a citten report upon completion of the re-evaluation program. The report shall include the following information.

(1) Describe, in detail, the function of the masonry walls.

the configurations of these walls, the type and strengths of che materials of which they are constructed (mortar, grout, concrete and steel), and the reinforcement details (horizontal steel, vertical steel, and masonry ties for multiple wythe construction). A wythe is considered to be (as defined by ACI Standard 531-1979) "each continuous vertical section of a wall, one masonry unit or grout'd space in thickness and 2 in. minimum in thickness."

Response

See attachment 2 of the July 11, 1980 submittal Appendix 7.4 of the attached Topical Report and enclosure 8 of the Ncvember 11, 1980 submittal.

Item 25 (ii) Describe the construction practices employed in the con-struction of these walls and, in particular, their ade-quacy in preventing significant voids or other weaknesses in any mortar, grout, or concrete fill.

Response

See enclosure 8 of the November 11, 1980 submittal.

_ Item 2b (iii) The re-evaluation report should include detailed justifica-tion for the criteria used.

References to existing codes or test data may be used if applicabic for the plant condi-tions. The re-evaluation should specifically address the following:

Response

See enclosures 2 and 5 of the November 11, 1980 submittal.

Item 2b (iii)

(a) All postulated loads and load combinations should be evaluated against the correspuding re-evaluation acceptance criteria. The re-evaluation should consider the loads from safety and non-safety-related attachments, differential floor displacement and thermal effects (or detailed justification that these can be considered self limiting and cannot induce brittle failures), and the effects of any potential cracking under dynamic loads. Desc-ibe in detail the methods used to account for these factors in the re-evaluation and the ade-quacy of the acceptance criteria for both in-plane and out-of-plane loads.

Response

See Appendix 7-2 of the att.'ched Topical Report and 2nclosures 2 and 3 of the November 11, 1980 submittal.

Iten 2b (iii)

(b) The mechanism for load transfer into the masonry walls ar.d postulated failure modes should be reviewed. For multiple wythe walls in which composite behavior is relied upon, des-cribe the methods and acceptance criteria used to assure that these walls will behave as composite walls, especially with regard to shear and tension transfer at the wythe inter-faces. With regard to local loadings such as piping and equipment support reactions, the acceptance criteria should assure that the loads are adequately transferred into the wall, such that any assumptions regarding the behavior of the walls are appropriate. Include the potential for block pullout and the necessity for tensile stress transfer through bond at the wythe interfaces.

2csponse See attached Topical Report paragraphs 4 and 5 and enclosures 2 and 3 of the November 11, 1980 submittal.

Item 3.

Existing test data or conservative assumptions may be used to justify the re-evaluation acceptance criteria if the criteria are shown to be conservative and applicable for the actual plant conditions.

In the absence of appropriate acceptance criteria a confirmatory masonry wall test program is required by the NRC in order to quantify the safety margins inherent in the re-evalua-tion criteria. Describe in detail the actions planned and their schedule to justify the re-evaluation criteria used in Item 2.

If a test program is necessary, provide your commitment for such a program and a schedule for submittal of a description of the test program and a schedule for completion of the program.

This 4

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Item 3.

test program should address all appropriate loads (seismic, tornado, missile, etc.).

It is expected that.the test program will extend beyond the 180 day period allowed for the other Bulletin actions. Submit the results of the test program upon its coopletion.

Response

See e, closure 3 of the November 11, 1980 submittal.

4 s'_

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THREE MILE ISLAND UNIT I REEVALUATION OF SAFETY-RELATED CONCRETE MASONRY WALLS NRC IE BULLETIN 80-11 TOPICAL REPORT NO. 001 REV. O I

I I

I PROJECT NO:

1101 AUTHORS

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DATE Tdly l A-190l AP OVAL 7/ly/g/

NbANAGER DATE l

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VICE PRESIDENT DA'rE TECHNICAL FUNCTIONS (SIGNIFICANT IMPACT REVIEW)

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TECHNICAL INFORMATION REPORT RECORD OF REVISION SHEET I

REVISION APPROVALS REVISION INITIALS AND DATES NUMBER DESCRIPTION OF REVISION RESP. ENGR. SEC. MGR.

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I TABLE OF CONTENTS I

Abstract Title Page No.

a.

Brief Statement of Problem 1

I b.

Summary of key results 1

c.

Conclusion 1

d.

Recommendations 1

Section

1.0 INTRODUCTION

2 2.0 METHODS 2

3.0 RESULTS 2

I

4.0 CONCLUSION

S 3

5.0 RECOMMENDATIONS 3

6.0 REFERENCES

7.0 APPBNDICES 1.

General arrangement of block walls I

affected by IE Bulletin 80-11.

2.

Summary of Stresses 3.

In-plane Drift Effects 4.

Block Wall Sketches 5.

Floor Response Spectra Curves I

I I

ABSTRACT a.

Brief Statement of Problem The USNRC IE Bulletin 80-11 dated May 8, 1980 requires I

that all power reactor facilities with an operating license to:

1.

Identify all masonry walls in the facility which are in proximity to or have attachments from safety-related piping or equipment such that wall failure could affect a safety-related system.

2.

Provide a reevaluation of the design adequacy of the walls identified in Item 1 above to determine whether the masonry walls will perform their

,I intended function under cll postulated loads and load combinations.

b.

Summary of Key Results The resultant stresses and in-plane drift effects from

I the analysis based on the Reevaluation Criteria and ACI 531-79 are summarized in Appendices as follows:

Appendix 7.5 Stress Summary I

Appendix 7.6 In-plane Drift Effects c.

Conclusions The results of the block wall analysis indicate that all fourteen walls are qualified satisfying the stress acceptance Criteria contingent upon the repair I

modifications listed in the Recommendations below.

d.

Recommendations I

The following modifications must be implemented in order to justify the assumptions made in the analysis.

1.

Auxiliary Building The collar joints of all composite (multiple I

wythe) block wall construction must be filled with non-shrink Portland Cement Grout.

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1

~ I ifI ABSTRACT (Cont'd)

I 2.

Reactor Build ng i

1

) l Provide steel brackets to reinforce the end spans E

of the North and South walls of the elevator shaft.

I' g Reinforce the North wall of the elevator shaft by j, g providing horizontal steel frame midway between elevations 308 and 346 feet to cut down the i

vertical span.

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I 1.0 PURPOSE AND SlnMMARY The purpose of this reevaluation is to determine the struc-tural adequacy of the concrete masonry walls in accordance with the NRC IE Bulletin 80-11.

The reevaluation shall determine whether the walls will per-form their intended function under all postulated loads and load combinations specified in the " Criteria for the I

Reevaluation of Concrete Masonry Walls," which is consistent with the requirements specified in item 2b of the Bulletin.

I In our letter of November 11, 1980 (TLL 584) sixteen walls were identified to be affected by the Bulletin.

However, wall AB-14 being in a highly contaminated area was excluded from analysis at this time.

TB-1 was reevaluated and it was I

determined that no safety-related equipment is on or in proximity to this wall.

The reevaluation for the remaining 14 walls was performed and the results are included in this report.

2.0 METHODS All walls chosen for reevaluation were subjected to all postulated loads and load combinations specified in the Reevaluation Criteria.

I The analysis was performed in accordance with Section 6 of the Reevaluation Criteria.

The natural frequency and resultant stresses were determined by either the finite element method or exact solution depending upon configuration of the wall, openings, attach-I ment loads, etc.

Ansys Computer program was used in performing the analysis.

I None of the L30ck walls are intended to resist impact or pressurization..oads, nor would they be subjected to a significant thermal load to be of any concern.

3.0 RESULTS The results of the block wall analysis including the six I

walls submitted previously are summarized in the Appendices below:

g Appendix 7.2 Summary of Stresses p

Appendix 7.3 In-Plane Drift Effects Appendix 7.4 Block Wall Sketches I

I 2

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4.0 CONCLUSION

S 4.1 Auxiliary Building During a field survey, no collar joint was found at any I

of the multi-wythe block walls.

The existence of collar joints is essential for combined action of the walls and to transfer the attachment loads to the internal wythe having shear keys to carry the load to the main struc-I ture.

The resultant stresses from the analysis show that all fifteen walls in auxiliary building are able to sustain the postulated load combinations contingent upon I

the repair modification listed in the recommendations below.

The in-plane drift effects, due to seismic loads, are insignificant compared to the Reevaluation Criteria.

4.2 Reactor Building The results of the elevator shaft analysis indicate that portions of the North and South walls will have to be reinforced, as per recommendations below to satisfy the stress limits specified in the Reevaluation Criteria.

5.0 RECOMMENDATIONS 5.1 Auxiliary Building The collar joints of all composite (multiple wythe) block walls shall be filled with non-shrink Portland Cement Grout.

5.2 Reactor Building Tne end spans of North and South walls must be rein-forced by prov.iding steel brackets to carry the seismic I

loads to the st,el columns.

Provide a horizontal steel frame between elevations 308' and 346' to provide lateral support to the East block wall.

6.0 REFERENCES

1.

ACI 531-79 " Building Code Requirements for Concrete Masonry Structures."

2.

Criteria for Reevaluation of Concrete Masonry Walls.

I Three Mile Island Nuclear Station Unit 1.

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APPENDIX 7.1 i

l General Arrangeme.,t of Block k' alls Tnat are Affected by IE Bulletin 80-11 I

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ML20010F797

Contents

Text

Dear Sir:

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1.0 INTRODUCTION

4.0 CONCLUSION

6.0 REFERENCES

4.0 CONCLUSION

6.0 REFERENCES

SUMMARY

.

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ML20010F797

Text

Dear Sir:

Response

Response

Response

Response

Response

Response

Response

1.0 INTRODUCTION

4.0 CONCLUSION

6.0 REFERENCES

4.0 CONCLUSION

6.0 REFERENCES

SUMMARY

.

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