Text

Rept on Settlement of Major Plant Structures
	ML20212J238
Person / Time
Site:	Hatch
Issue date:	05/31/1986
From:	; BECHTEL GROUP, INC.
To:	;
Shared Package
ML20212J149	List: ML20212J144; ML20212J238;
References
	TAC-11158, NUDOCS 8701280113
	Download: ML20212J238 (125)
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SOUTHERN COMPANY SERVICES BY BECHTEL POWER CORPORATION GAITHERSBURG, MARYLAND E'

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1 E. I. HATCH NUCLEAR POWER PLANT UNITS 1 AND 2

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REPORTONSETiLEMENTOF MAJOR PLANT STRUCTURES FOR GEORGIA POWER COMPANY n.

SOUTHERN COMPANY SERVICES

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TABLE OF CONTENTS

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PAGE

1. 0 INTRODUCTION AND SCOPE 1

2. 0 PREDICTED SETTLEMENT 2

3.0 SETTLEMENT MONITORING DATA 3

4.0 TOTAL SETTLEMENT 3

5. 0 DIFFERENTIAL SETTLEMENT ACROSS STRUCTURES (TILT) 5

6. 0 PENETRATION DIFFERENTIAL SETTLEMENT 7

7. 0 FREQUENCY OF READINGS 8

8. 0 ACCURACY OF READINGS 9

9. 0 TECHNICAL SPECIFICATION 3/4.7.8 10

10.0 CONCLUSION

S AND RECOMMENDATIONS 12 REFERENCES 15 I

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TABLE OF CONTENTS (Continued)

TABLES t

TABLE 1:

PREDICTED AND MEASURED TOTAL SETTLEMENTS TABLE 2:

SUMMARY

OF DIFFERENTIAL SETTLEMENTS ACROSS STRUCTURES TABLE 3:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND SOIL TABLE 4:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS DIESEL GENERATOR BUILDING AND SOIL TABLE 5:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS MAIN STACK AND SOIL TABLE 6:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS INTAKE STRUCTURE AND SOIL 6

TABLE 7:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND RADWASTE BUILDING HNP-2 e

TABLE 8:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND CONTROL BUILDING TABLE 9:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND TURBINE BUILDING HNP-2 TABLE 10:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND REACTOR BUILDING HNP-1 b

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TABLE OF CONTENTS (Continued)

FIGURES F5GURE 1:

POWER BLOCK BENCHMARK AND PENETRATION LOCATIONS FIGURE 2:

BENCHMARK AND PENETRATION LOCATIONS FOR OFFGAS STACK, 3

INTAKE STRUCTURE AND DIESEL GENERATOR BUILDING FIGURE 3:

REACTOR BUILDING UNIT 1 BENCHMARK SETTLEMENT s

FIGURE 4:

REACTOR BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 5:

RADWASTE BUILDING UNIT 1 BENCHMARK SETTLEMENT FIGURE 6:

RADWASTE BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 7:

TURBINE BUILDING UNIT 1 BENCHMARK SETTLEMENT FIGURE 8:

TURBINE BUILDING UNIT 2 BENCHMARK SETTLEMENT CONTR'L BUILDING BENCHMARK SETTLEMENT FIGURE 9:

O FIGURE 10: DIESEL GENERATOR BUILDING BENCHMARK SETTLEMENT FIGURE 11:

INTAKE STRUCTURE BENCHMARK SETTLEMENT l

FIGURE 12: OFFGAS (MAIN) STACK BENCHMARK SETTLEMENT i

FIGURE 13: REFERENCE BENCHMARK LOCATIONS 4

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TABLE OF CONTENTS (Continued) f.

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APPENDICES APPENDIX A:

TECHNICAL SPECIFICATION 3/4.7.8, SETTLEMENT OF CLASS 1 STRUCTURES 3

APPENDIX B:

SETTLEMENT DATA - REACTOR BUILDING UNITS 1 AND 2 APPENDIX C:

SETTLEMENT DATA - RADWASTE BUILDING UNITS 1 AND 2 2

APPENDIX D:

SETTLEMENT DATA - TURBINE BUILDING UNITS 1 AND 2 APPENDIX E:

SETTLEMENT DATA - CONTROL BUILDING AND DIESEL GENERATOR BUILDING APPENDIX F:

SETTLEMENT DATA - INTAKE 6TRUCTURE AND OFFGAS (MAIN)

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k$ d-h" EXECUTIVE

SUMMARY

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i All available information and measurement dat.a on the iled, and toring of E. I. Hatch Nuclear Power Plant structures were co the data plotted and analyzed.

dies r re the Final Safety Analysis Report, and previous related stu reviewed as part of this comprehensive study.

d The results show that the butidin.g settlements have essentially st P,

l The several years ago, and are all below the predicted maximum va ues.

Based on dif ferential settlements are also below the allowable limits.for the past p

the conclusion of no significant building settlementi tion 3/4.7.8 years, it is recommended that the current Technical Specif ca The outline contained be replaced with a Plant Operating Procedure.

this recommended within this report is intended to serve as a basis for I

change.

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1.0 IgTRODUCTIONANDSCOPE I

As(requiredbyTechnicalSpecification3/4.7.8, entitled

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" Settlement of Class 1 Structures," Georgia Power Company (GPC) is committed to monitor total and differential settlements of I

all Class 1 structures'at E. I. Hatch Nuclear Plant Unit 2 (HNP-2). The technical specification was issued in 1978 and l

has included the monitoring of not only the Unit 2 Class 1 structures but other major plant structures.

The structures included are listed below:

o Reactor Building, Units 1 and 2 l

o Turbine Building, Units 1 and 2 l

0 Radwaste Building, Units 1 and 2 j

o Control Building

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Olesel Generator Butiding o

Intake Structure o

Offgas (Main) Stack i

The technical specification, which is included as Appendix A, outlines the monitoring and the resulting potential action requirements for the Class 1 structures.

The major structures at Plant Hatch were constructed in the l

early to mid-1970's, with commercial operation for Unit 1 and Unit 2 being December 1975 and September 1979, respectively.

Since the start of commercial operation, the measured settle-ments of all structures have stabilized to nearly constant I

values.

In light of this, the purpose of this report is to perform a comprehensive review of the technical specification 1

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EXECUTIVE

SUMMARY

i t-All available information and measurement data on the settlement moni-toring of E. I. Hatch Nuclear Power Plant structures were compiled, and the data plotted and analyzed..The applicable Technical Specif.ication, the Final Safety Analysis Report, and previous related studies were reviewed as part of this comprehensive study.

8 The results show that the building settlements have essentially stopped I

several years ago, and are all below the predicted maximum values.

The differential settlements are also below.the allowable limits.

Based on the conclusion of no significant building settlement for the past several t

years, it is recommended that the current Technical Specification 3/4.7.8 be replaced with a Plant Operating Procedure.

The outline contained within this report is intended to serve as a basis for this recommended change.

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TABLE OF CONTENTS (Continued) l APPENDICES E

TECHNICAL SPECIFICATION 3/4.7.8, SETTLEMENT OF CLASS 1 APPENDIX A:

STRUCTURES APPENDIX B:

SETTLEMENT DATA - REACTOR BUILDING UNITS 1 AND 2 APPENDIX C:

SETTLEMENT DATA - RADWASTE BUILDING UNITS 1 AND 2 APPENDIX D:

SETTLEMENT DATA - TURBINE BUILDING UNITS 1 AND 2 APPENDIX E:

SETTLEMENT DATA - CONTROL BUILDING AND DIESEL GENERATOR BUILDING APPENDIX F:

SETTLEMENT DATA - INTAKE STRUCTURE AND OFFGAS (MAIN)

STACK I

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8 TABLE OF CONTENTS (Continued)

FIGURES

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FIGURE 1:

POWER BLOCK BENCHMARK AND PENETRATION LOCATIONS FIGURE 2:

BENCHMARK AND PENETRATION LOCATIONS FOR OFFGAS STACK, INTAKE STRUCTURE AND DIESEL GENERATOR BUILDING FIGURE 3:

REACTOR BUILDING UNIT 1 BENCHMARK SETTLEMENT FIGURE 4:

REACTOR BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 5:

RADWASTE BUILDING UNIT 1 BENCHMARK SETTLEMENT FIGURE 6:

RADWASTE BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 7:

TURBINE BUILDING UNIT 1 BENCHMARK SETTLEMENT FIGURE 8:

TURBINE BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 9:

CONTROL BUILDING BENCHMARK SETTLEMENT FIGURE 10: DIESEL GENERATOR BUILDING BENCHMARK SETTLEMENT FIGURE 11:

INTAKE STRUCTURE BENCHMARK SETTLEMENT FIGURE 12: OFFGAS (MAIN) STACK BENCHMARK SETTLEMENT FIGURE 13:

REFERENCE BENCHMARK LOCATIONS I

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TABLE OF CONTENTS (Continued)

TABLES TABLE 1:

PREDICTED AND MEASURED TOTAL SETTLEMENTS TABLE 2:

SUMMARY

OF DIFFERENTIAL SETTLEMENTS ACROSS STRUCTURES E

TABLE 3:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND SOIL I

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS TABLE 4:

DIESEL GENERATOR BUILDING AND SOIL TABLE 5:

SUMMARY

OF PENETRATION. DIFFERENTIAL SETTLEMENTS MAIN STACK AND SOIL TABLE 6:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS INTAKE STRUCTURE AND SOIL TABLE 7:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND RADWASTE BUILDING HNP-2 TABLE 8:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND CONTROL BUILDING TABLE 9:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND TURBINE BUILDING HNP-2 TABLE 10:

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND REACTOR BUILDING HNP-1 8

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TABLE OF CONTENTS k

PAGE

1.0 INTRODUCTION

AND SCOPE 1

2. 0 PREDICTED SETTLEMENT 2

3.0 SETTLEMENT MONITORING DATA' 3

4.0 TOTAL SETTLEMENT 3

S.0 DIFFERENTIAL SETTLEMENT ACROSS STRUCTURES (TILT)

S 6.0 PENETRATION DIFFERENTIAL SETTLEMENT 7

7. 0 FREQUENCY OF READINGS 8

8.0 ACCURACY OF READINGS 9

9.0 TECHNICAL SPECIFICATION 3/4.7.8 10

10.0 CONCLUSION

S AND RECOMMENDATIONS 12 REFERENCES 15 I

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l E. I. HATCH NUCLEAR POWER PLANT UNITS 1 AND 2 5

E REPORT ON SETTLEMENT OF I

MAJOR PLANT STRUCTURES I

FOR GEORGIA POWER COMPANY SOUTHERN COMPANY SERVICES BY BECHTEL POWER CORPORATION GAITHERSBURG, MARYLAND E

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,in conjunction with the settlement measurements recorded to rjateforeachstructure.

In addition, it will be deterteined if thanges can be made to Technical Specification 3/4.7.8, while continuing to assure that plant safety and operations are maintained.

The following items will be addressed:

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o Total Settlement Differential Settlement Across Structures (Tilt) o Penetration Differential Settlement (Between adjacent o

structures and between structures and soil) o Frequency of R6adings o

Accuracy of Readings o

Technical Specification 3/4.7.8 l

2.0 PREDICTED SETTLEMENT Settlement predictions were made for the structures under con-sideration. Generally, the prediction util'ized stress values calculated in accordance with the Westergaard theory and considered stress overlap from all nearby founbations. Struc-tural dead loads plus live loads were considered in the stress calculation.

The soil compressibility characteristics were

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cetermined by one-dimensional laboratory consolidation tests.

't Details of the settlement estimate are given in the Final f

Safety Analysis Report (FSAR) Section PA.5.3, Reference 1.

p Table 1 presents the predicted total settlement for each li structure under consideration.

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3. 0 SETTLEMENT MONITORING DATA

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fheconclusionsandrecommendatio'nsofthisreportarebasedon i

lettlement monitoring data supplied by GPC and information contained in the FSAR Section 2A.5.3.

In most cases, information

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from these two sources provides a complete record of settlement for each structure, except for the following:

I li Reactor Building Unit 2 no data was available for 1973 e

o and 1974 r>

Turbine Building Unit 1 - no data was available for 1972 o

and 1974 Control Building - no data was available for 1972 o

Diesel Generator Building - no zero readings were available o

for the NE and NW benchmarks Radwaste Building Unit 1 no data was available for 1972 o

s Intake Structure no data was available prior to mid-1978 o

A In all cases, however, sufficient information is available to

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determine settlement trends and maximum settlement for each p

structure and to determine what future course of action is required.

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4.0 TOTAL SETTLEMENT 1

Measurements of structure movements w: e, in most cases, made h

once each month during construction and have been made twice a 9

year since each structure has been completed. The measurements 7

are currently being made on four settlement benchmarks established g

on each structure, except for the Offgas (Main) Stack where there are only three benchmarks.

Figure 1 shows the relative

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I locations of each benchmark on the power block structures,

--while Figure 2 shows the relative locations of each benchmark r

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.for the Offgas (Main) Stack, Diesel Generator Building r.d lIntake Structure.

The tabulated total settlements for each structure are given in 8

Appendices B through F.

The values were determined by subtrac-ting the survey reading for a given date from the total set-q tlement reference elevation established near the start of 6;

construction. However, in some cases (generally prior to 1975), only the measured settlements were provided in the supplied data.

Further, where tabulated survey data were not

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available, settlement figures from the FSAR were used to

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estimate the movement of a particular benchmark.

1 I rr Several assumptions and adjustments to the reference elevations l

L were made in order to determine the actual benchmark movement.

f For example, referring to Appendix B, the reference elevation for the southwest marker of the Reactor Building Unit 2 was I

130.002 feet. On January 15, 1980, the survey reading indi-cated the southwest marker had settled a total of 1.884 inches (0.157 feet) since the beginning of settlement monitoring.

On the same day, a new settlement benchmark was established.

The surveyed elevation of 129.859 feet for the replacement bench-mark was adjusted to 130.016 feet (129.859 + 0,.157) to account s

j for the. settlement which had already taken place.

Subsequent readings were then compared directly to the new established reference elevation of 130.016 feet.

Details of these assump-tions and adjustments are given in Appendices B through F.

Settlement versus time curves for each structure, prepared from the data contained in Appendices B through F, are presented as Figures 3 through 12.

Common vertical and horizontal scales were used for each plot for ease of ccmparison of relative amounts of movement with respect to time.

4

4,I The ratios of the measured settlements (both historical maximum

~and as of July 1985) to the predicted settlements are shown in Table 1.

The ratios are highest'at the Unit 1 Reactor and Turbine Buildings and the Control Building. All three of these structures were completed during the early construction stages at riant Hatch. The ratios for the Unit 2 structures are lower due to higher predicted Unit 2 settlements, and because Unit I structures partially prestressed or preloaded the soil beneath f*,

the Unit 2 structures prior to the start of Unit 2 construction and settlement monitoring.

As shown on Figures 3 through 12, the settlement curves have flattened out, indicating th5t no measureable settlement of any structure has occurred for at least the last seven years.

It is believed that the slight cyclic movements taking place are due to the inherent variations associated with optical survey, including seasonal variation with temperature. These curves 1.

demonstrate that the structures have essentially completed their settlements, and that the measured settlement values will not reach the predicted values.

5.0 DIFFERENTIAL SETTLEMENT ACROSS STRUCTURES (TILT)

Differential settlement across buildings will only be con-sidered for those structures referenced in theiE. I. Hatch s.

Nuclear Plant Unit 2 (HNP-2) FSAR, Section 2A.S.3.2.

Those structures are:

o Reactor Building Unit 2 o

Radwaste Building Unit 2 o

Turbine Building Unit 2 o

Control Building l

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o Diesel Generator Building i

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g Offgas (Main) Stack i

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o Intake Structure PW Details of the criteria used to establish the allowable differ-a ential settlement across each structure are not discussed here.

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but can be found in FSAR Section 2A.5.3.2.1, and in Reference 2.

To determine the actual differential settlements, tilt reference ry

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elevations have been established for the settlement benchmarks in each building. The term 'Itilt reference elevation" used here is the elevation which can be compared with current survey elevation readings to indicate the existing degree of differential f

settlement across the structure.

These tilt reference elevations 3*

are based on the survey readings taken at or near the construction 7

completion date of each buf1 ding. This date corresponds to the time when the structure is assumed to be properly aligned, both L

with respect to itself and to any adjacent building. ' Existing

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differential settlement across the structure will be measured from this reference date and compared with the allowable h

values.

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Using the tilt reference elevations and the latest survey d

values, the settlement of each benchmark from the reference 3

date to the present time can be determined. A comparison of the settlement values of any two benchmarks within a building provides the differential settlement or tilt between the k

benchmarks.

A comparison of the existing and allowable differential settle-ments is shown in Table 2, along with the reference date (approximate completion date of each structure). The results indica ~te that there has been little differential settlement to date and that the existing tilt is well below the allowable.

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urther, by examining the settlement u rves (Figures 3 through B

2), it is apparent the differential settlement across all tructures will not significantly change in the future, as each structure has reached an equilibrium point and no additional measureable movement is expected.

6.0 PENETRATION DIFFERENTIAL SETTLEMENT 5

Penetration differential settlements for those structures referenced in the FSAR Section 2A.S.3.3, will be considered here.

The structures considered are the same as listed in I

Section 5.0.

The only exceptions are the penetrations between each Reactor Building, which will also be addressed.

Details of the criteria used to establish the allowable differ-ential settlement for the penetrations are not discussed,here, but can be found in FSAR Section 2A.5.3.3.1 and in Reference 2.

I Differential settlements of the penetrations since installation were measured by assuming the settlement of the penetration to be the same as the settlement of the nearest benchmark.

For each penetration exiting from the structure into the scoil, reference was made to the appropriate value of settlement given l

in Appendices B through F.

This value of settlement was compared to the latest (July 1985) movement of' the benchmark (either up or down), which had occurred since the date of pene-tration completion.

If no reading was taken for a benchmark cn the completion date, then the previous reading was used as the I

reference value.

It should be noted that the maximum movement is not necessarily the movement that occurred between the penetration completion date and the present reading. This is because the settlement pattern of all of the benchmarks is, at present, nearly level, with dips and peaks due to inherent I

survey error and thermal expansion and contraction of the structures. As a result, the maximum settlement frequently occurs in one of the dips measured prior to the present readings.

7 B

f For penetrations passing between adjacent structures, the pettlementofthebenchmarksclosesttothepenetrationonboth structures must be considered. The settlement values of the two benchmarks from the penetration installation date to present are compared to the latest (July 1985) mcvement. A review indicates that maximum differential settlement does not necessarily occur on the most recent date for the reasons stated in the previous paragraph.

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The ratios of the maximum measured settlement to the allowable settlement for the penetrations have been calculated and are rv presented in Tables 3 through 10. These tables show that all 6.

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of the measured settlements are presently well below the allowable values, with the large majority being less than 20 percent of the allowable. These low ratios reflect two n

related f. actors:

first, the majority of the penetrations have bees, installed since late 1976; and second, building settlement r

values since late 1976 have been very small.

t Examination of the settlement curves on Figures 3 through 12 n

shows that the differential settlements at the penetrations have not changed significantly in the last seven years.

Since the curves indicate that the structures have essentially completed their settlement, this pattern of "no change" is r,

expected to continue in the future.

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7.0 FREQUENCY OF READINGS Presently, the benchmarks are being surveyed twice a year, except when the benchmark is temporarily blocked by equipment or if radiation is high, as in the case of the Offgas (Main)

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Stack. Generally, the readings are taken near the beginning of i

the year, in January, and in the middle of the year, in July.

r This monitoring pattern has resulted in what appears to be small cyclic temperature fluctuations.

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T 8.0 ACCURACY OF READINGS The settlement values are determined by measurements which are kompared with known elevations at established onsite reference k,

benchmarks. The locations of the reference benchmarks are O

shown on Figure 13. The elevations of the reference benchmarks were originally established from a United States Geological Survey (USGS) benchmark in Toombs County.

The reference benchmarks are situated in the yard in such a way as to avoid k

accidental displacement and facilitate the settlement surveys of the Class 1 buildings. They are far enough away to avoid settling with the buildings.

Precautions were also taken to

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provide proper soil and anchorage conditions to ensure the P

stability of the benchmarks.

However, there appears to be no procedure for periodically checking the elevations of the

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reference benchmarks.

Plant operating procedure 42SV-SUV-014-2 established a detailed method for monitoring settlement of Class 1 structures for HNP-1 and HNP-2.

A series of special drawings was prepared to

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clearly locate the benchmarks and establish a fixed survey route. These drawings are referenced in the procedure. The

fs acceptance criterion for closure error is 0.005 foot.

The 6

procedure establishes as much consistency as possible from one survey to the next in order to make any change;or abnormality immediately apparent. However, even with tight controls, survey " errors" and variations are inevitable.

These can be divided into three categories:

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Instrumental errors o

Personal errors o

Natural variations T

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F Ideally, the plant operating procedure eliminates the instru-I-

~ hntal and personal " errors" through a system of checks and plances.

The natural variations, however, are unpredictable.

re Surveying experience indicates the variations associated with

.L optical leveling can be as high as 11/8 inch (Reference 3),

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which is about the level of accuracy that can be expected for a first order survey traversing about 1/4 mile (Reference 4).

.s Most of this is more than likely due to natural " variations,"

such as temperature fluctuations, that occur during the survey.

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9. 0 TECHNICAL SPECIFICATION 3/4.7.8 In order to understand the development and implementation of the technical specification, a brief chronology of significant events is given below:

L o

June 13, 1978: Nuclear Regulatory Commission (NRC) issued F

the Plant Hatch Unit 2 Technical Specification for Monitoring Building Settlement 3/4.7.8.

7 o

June 15, 1978: GPC requested Bechtel to "... investigate the potential significance of building settlement and review the specification that the NRC issued..."

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November 1978: Bechtel issued a report entitled, " Proposed Technical Specification, Settlement of Category I Struc-tures," as an outgrowth of the June 15, 1978 GPC request.

o December 1, 1978:

GPC transmitted to the NRC the proposed changes to Technical Specification 3/4.7.8.

o March 30, 1979:

NRC requested additional information re-garding December 1, 1978 GPC submittal.

o July 20, 1979: NRC requested additional information re-garding December 1, 1978 GPC submittal.

10

F o

August 14, 1979: GPC responded to March 30, 1979 NRC request.

5 October 8, 1979: GPC responded to July 20, 1979 NRC request.

d o

September 27, 1982:

GPC proposed to the NRC deleting Technical Specification 3/4.7.8 and a withdrawal of sub -

mittals on that subject.

o December 7, 1983: GPC outlined to the NRC a procedure to L,

be used for continuation of settlement monitoring via a Plant Operating Procedure'.

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o May 4, 1984: GPC reported to the NRC a possible error in 7

the December 7, 1983 submittal and discrepancies between t-the FSAR and Technical Specification 3/4.7.8.

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o October 1985: GPC requested that Bechtel review the set-tiement issue, including all submittals to the NRG on n

building settlement, and recommend changes needed to Technical. Specification 3/4.7.8, if appropriate.

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o December 18, 1985: GPC reported to the NRC that the

[s December 7, 1983 submittal was incorrect. iThe correct L3 information was supplied.

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April 4, 1986: GPC reiterated the September 27, 1982 submittal to delete Technical Specification 3/4.7.8 and monitor building settlement via a Plant Operating Procedure.

f The original technical specification, which was initially B

reviewed in 1978, is the same Technical Specification 3/4.7.8 still in use today and given in Appendix A.

The only difference between the two is that the original 1978 version gave an allowable differential settlement of 3/4 inch for all structures, i

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whereas the current version does not give allowable differential ettlement values. GPC has initiated action with the NRC to

[esolvethisdifference.

Further', GPC has committed to monitor Building settleraent in accordance with provisions given in the n

y FSAR, Section 2A.5.3, via a plant operating procedure rather than a Technical Specification.

fro It must be emphasized that whether or not differential settle-y ment is addressed in the Technical Specification, it does not alter the fact the structures are not settling and are not expected to settle in the future.

It is for this reason that y

the Technical Specification can be eliminated.

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10.0 CONCLUSION

S AND RECOMMENDATIONS u.

The settlement curves on Figures 3 through 12 demonstrate that the structures under consideration are not settling and have q

not been settling for at least the last seven years.

In every case the measured total settlement (Table 1) for each structure is less than the predicted value. The small movements that have taken place recently appear to be due to temperature

[f:

fluctuation and the inherent variation in optical surveys..

Further, no appreciable tilt has occurred in any of the struc-tures.

In all cases, the ratio of measured differential

{s settlement to the allowable differential settlement (across y

structures) is less than or equal to 30 percent (Table 2).

The L

ratio of the measured differential settlement to the allowable differential settlements (for penetrations) is less than or equal to 53 percent (Tables 3 through 10).

In summary, the structures have experienced all of the appreciable settlement that is expected to occur, and any remaining measured movement f

will be due to survey inaccuracies and/or temperature fluctu-a4. ions.

In conclusion, from a purely geotechnical standpoint, Technical Specification 3/4.7.8 can be eliminated in its entirety and i

12 m

~

PW settlement monitoring of the structures can be accomplished brough a Plant Hatch Operating Procedure, t'is recommended that the new procedure address not only total settlements, but differential settlements as well. The basis for the plant operating procedure is the December 1,1978 submittal from GPC to 'the NRC, Reference 5, with some minor revisions. Note that the provisions in Reference 5 are the

'f same as those in Reference 2 and in Section 2A.S.3 of the FSAR.

N The recommended criteria to be used to evaluate the settlements 2

are as described below:

u A.

Surveillance Requirements'

?-

The surveillance requirements for all settlement benchmarks shall be once a year, except when an unusual meteorological b

or seismic event occurs, in which case the structures should be surveyed as soon as possible.

The existing r

surveillance requirements 4.7.8 a and b of Technical s

Specification 3/4.7.8 should be deleted in their entirety.

s B.

Total Settlement h

The total settlement of each structure shall not exceed the predicted values given in Table 1.

If theitotal settlement of any structure reaches the predicted settlement given in Table 1, GPC site engineering should notify GPC corporate engineering for resolution.

[

C.

Differential Settlement Across Structures The differential settlement across structures shall not f

exceed the allowable values given in Table 2.

If the differential settlement across any structure exceeds 75 percent of the allowable settlement value given in Table 2, 13

m GPC site engineering should notify GPC corporate engineering for resolution.

Penetration Differential Settlement Between Structure and f

Soil The penetration differential settlement between structure and soil shall not exceed the allowable values given in

?

Tables 3 through 6.

If the penetration differential settlement between structure and soil exceeds 75 percent of 2-the allowable values given in Tables 3 through 6, GPC site engineering should notify GPC corporate engineering for s.

resolution.

r s.

E.

Penetration Differential Settlement Between Adjacent N

Structures b

p The penetration differential settlement between structures shall not exceed the allowable values given in Tables 7 s

through 10.

If the penetration differential settlement t

between adjacent structures exceeds 75 percent of the allowable values given in Tables 7.through 10, GPC site engineering should notify GPC corporate engineering for resolution.

f, 1

Lt further, it is recommended that provisions be incorporated in the procedure to check the elevations of the reference bench-y marks, shown on Figure 13, at least once every 5 years or if it is suspected that damage to the reference benchmarks has occurred.

14

i F

t REFERENCES

[

1.

Final Safety Analysis Report (FSAR) Update, E. I. Hatch Nuclear 3

Plant, Unit 2, Georgia Power Company.

I 9

2.

Proposed Technical Specification, Settlement of Category I Struc-r tures, E. I. Hatch Nuclear Plant, Unit 2, Bechtel Power Corporation, November 1978.

v, 3.

Lewis, M. R., and A. Sanver, Foundation Movement Monitoring of a-Heavy Structures - A Case History," International Conference on Case r,

Histories in Geotechnical Engineering, University of Missouri-Rolla, Rolla, Missouri, May 1984.

't 4.

Merrit, Frederick S., " Standard Handbook for Civil Engineers," New

~

York: McGraw-Hill Book Company, 1968.

~

5.

Letter from C. F. Whitmer (GPC) to Director of Nuclear Reaclor Regulation (NRC), dated December 1, 1978.

m m b

+

e i

N' b

w e

4 Y

k I

L 15 7

L

'N-R F

4 N

e t

l i

6 b

TABLES T,.

7-t e

5O' S

bo P

L i

6 9

k l

m I.

~

TABLE 1 PREDICTED AND MEASURED TOTAL SETTLEMENTS RATIO OF MEASURED SETTLEMENT-INCHES 1 TO PREDICTED-%

MEASURED STRUCTURE PREDICTED MAXIMUM TO DATEz MAXIMUM TO DATE2 Reactor Building Unit 1 3.1 2.8 2.6 90 84 i

Reactor Building Unit 2 4.5 2.0 1.7 44 38 Turbine Building Unit 1 1.5

1. 2 1.2 80 80 Turbine Building Unit 2 2.0

0. 3 15 Radwaste Building Unit 1 1.5 0.8 0.6 53 40 Radwaste Building Unit 2 3.5

- 0.5 0.3 14 9

Control Building 2.0

1. 5 1.5 75 75 Diesel Generator Building 2.0

1. 0

1. 0 50 50

?

Offga: (Main) Stack 2.0 0.4 0.3 20 15 Intake Structure 2.0 1.44 1.44 70 70 b

5 i

\\

1 7,

1 Settlements are reported to the nearest 0.1 inch.

2 July 1985 reading.

f aAll measurements are currently indicating heave.

(

4 Measured settlements are estimates only, since complete records do not exist prior to July 1978.

Ty

?

r--

TABLE 2

}.

SUMMARY

OFDIFFERENTIALSETTLEMENTSACROSSSTRUCTURES

~

(

DIFFERENTIAL RATIO 0F d

BETWEEN SETTLEMENT MEASURED REFERENCE DIRECTION BENCHMARK INCHES 2 TO ALLOWABLE STRUCTURE DATE OF TILT' NUMBERS 1 ALLOWABLE MEASURED 3 PERCENT Reactor 5-76 N-S 1 and 2 0.40 0.00 0

T.

Building N-S 3 and 4 0.41 0.02 5

Unit No. 2 E-W 1 and 3 1.67 0.12 7

E-W 2 and 4 1.61 0.10 6

7 Radwaste 10-75 N-S 5 and 6 1.85 0.28 15 Building N-S 7 and 8 1.92 0.30 16 Unit No. 2 E-W 5 and 7 1.58 0.01 1

{

E-W 6 and 8 0.96 0.04 4

Control 1-75 N-S 9 and 10 1.00 0.08 8

Building N-S 11 and 12 0.95 0.18 19

{~

E-W 9 and 11 3.01 0.22 7

E-W 10 and 12 3.46 0.12 3

7 Turbine 5-76 N-S 13 and 14 2.69 0.23

'9

['

Building N-S 154 and 16 2.46 0.29 12 Unit No. 2 E-W 13 and 154 2.96 0.19 6

7.;

E-W 14 and 16 3.37 0.13-4 s-Diesel 1-75 N-S 17 and 18 5.09 0.11 2

Generator-N-S 19 and 20 4.73 0.22 5

n Building E-W 17 and 19 2.47 0.43 17 E-W 18 and 20 2.47 0.11 4

r.

Offgas 10-74 N-S 21 and 22 0.44 0.13 30 (Main)

E-W 21 and 23 0.55 O.08 15 Stack E-W 22 and 23 0.50 0.05 10 Intake 10-74s N-S 24 and 25 2.50 0.24 10 Structure N-S 26 and 27 2.50 0.08 3

E-W 24 and 26 0.65 0.04 6

r E-W 25 and 27 1.25 0.12 10

'd d

2 Refer to Figure 1 for benchmark identification.

2Reported to the nearest 0.01 inch.

3 7

As of July 1985.

4No current survey data are available for benchmark 15; used last available cata, January 1979.

5Actual benchmarks used were established in July 1978.

2 o

M7 it

P5 TA8LE 3

..}'

m

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS

[

REACTOR 8UILDING HNP-2 AND SOIL J

Ratio of m

Differential Measured Settlement - Inches 1 to Allowable Date of Nearest Heasured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor U

8 in. No. 1 November 1977-1 0.13 0.73 1.03 13

' 18 7'

10 in. No. 2 December 1977 1

0.11 1.22 0.96 9

11 18 in. No. 3 April 1978 1

0.12 1.26 0.72 10 17 18 in. No. 4 March 1978 1

0.16 1.26 0.72 13 22 6 in. No. 8 November 1977 1

0.13 1.22 0.75 11 17 10 in. No. 10 January 1978 2

0.18 1.22 0.96 15 19 4

18 in. No. 11 March 1978 2

0.20 1.26 0.72 16 28 9

20 in. No. 12 January 1978 2

0.18 1.13 0.56 16 32 7

18 in. No. 13 April 1978 2

0.20 1.26 0.75-16 28

)'

14 in. No. 24 November 1977 2

0.18 1.15 1.06 16 17 10 in. No. 41 February 1977 2

0.10 1.28 0.88 8

11 16 in: No. 42 March 1978 2

0.20 1.06 0.73 19 27

[. I 14 in. No. 134 March 1978 1

0.16 1.15 1.13 14 14

.f 20 in. No. 161 January 1978 1

0.12 1.13 0.71 11 17 g.

P w

i T

i IReported to the nearest 0.01 inch.

2As cf July 1985.

Ir ia

(

.......,__.__.c.........___,,,_..

_,,,,,,,,_,m.

.~...M TABLE 4

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS

{

DIESEL GENERATOR BUILDING AND. SOIL i

E Ratio of Differential Measured '

Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 gr Pipe Anchor Pipe Anchor it, 6 in.

January 1978 17 0.20 0.57 0.57 35 35 10 in.

December 1971 17 0.493 0.92 53 8

I,

\\3 9

h e

r T

1 Reported to the nearest 0.01 inch.

2As of July 1985.

3 8 Earliest reading on Benchmark 17 is December 1972.

9?

?!h P

1

E E

TABLE 5

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS f

MAIN STACK AND SOIL E

Differential Ratio of E'

Settlement - Inchesi Measured Measured Allowable to Allowable Penetration Installation Benchmark to Date2 in Pipe Percent 18 in.

June 1974 23 0.04 0.45

'9 12 in.

May 1974 23 0 04 0.45 9

20 in.

June 1974 22 0.01 0.46 2

6 in.

May 1974 22 0.01 0.46 2

E F

E P.

at t

b P.

b 2 Reported *.o the nearest 0.01 inch.

2As of July 1985.

l

.-- _ ~

F

-i ; m j-F

-TABLE 6

~

SUMARY OF PENETRATION DIFFERENTIAL SETTLEMENTS f

INTAKE STRUCTURE AND SOIL E

Ratio of f

Date of Nearest Measured Allowable 3 Percent Differential Measurtd Settlement - Inches 1 to Allowable Penetration Installation Benchmark to Date Pipe Support Pipe Support rt 30 in.

January 1978 25 0.23 1.38 0.66 17 35 El. 97.28 ft.

er 12 in.

July 1974 25 0.23 0.99 1.19 23 19 18 in.

r.

(Unit 2)

February 1978 25 0.23 2.78 2.03 8

11 30 in.

January 1978 25 0.23 1.38 0.66 17 35

{

El. 91.75 ft.

(Unit 1) r 30 in.

January 1978 25 0.23 1.38 0.66 17 35 El. 91.75 ft.

(Unit 2)

I 18 in.

February 1978 27 0.11 2.47 1.27 4

9 s.

(Unit 1) r~'.

6 in.

April 1976 26 0.02 1.50 0.94 1-2 s.'

f'

'h e

l a

L 1

2 Reported to the nearest 0.01 inch.

{

y 2Measured differential settlements are estimates only, since complete records do not exist prior to July 1978. Measured settlements are as of July 1985.

8A11owable settlement is based on both pipe stress and support loads.

E E

TABLE 7 j.

SUP#tARY OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND RADWASTE BUILDING HNP-2 i

Ratio of

.:F Differential Measured Settlement - Inches 1 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 1 in. No. 51 October 1977 2 and 5 0.12 1.54 8

6 in. No. 51 October 1977 2 and 5 0.12 1.14 11 1.5 in. No. 102 November 1977 2 and 5 0.11 1.07 10 8 in. No. 153 February 1977 4 and 5 0.06 1.48 0.88 4

7 E

fl.

i y

?

L:

R b

b 2 Reported to the nearest 0.01 inch.

2As of July 1985.

s

TABLE 8

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS

{

REACTOR BUILDING HNP-2 AND CONTROL BUILDING

["

Ratio or Differential Measured r.

Settlement - Inches 1 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor rr L,

24 in. No. 59 May 1978 3 and 10 0.17 26.03 13.23 1

3 in. No. 60 January 1978 3 and 10 0.26 1.48 0.62 18 42 r-b-

18 in. No. 61 August 1977 3 and 1.0 0.27 9.55 1.86 3

15 7

24 in. No. 61 September 1976 3 and 10 0.19 12.14 5.06 2

4 3

4 in. No. 68 January 1978 3 and 10 0.26 1.84 0.85 14 31 w

4 in. No. 69 January 1978 3 and 10 0.26 1.99 0.78 l'3 33 s.

?'

3 "1

n;*

f' r-M b1 T

i 1 Reported to the nearest 0.01 inch.

l 2As of July 1985.

P a

et k

F F

TABLE 9

SUMMARY

OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND TURBINE BUILDING HNP-2 E

Ratio of m

Differential Measured Settlement - Inches 1 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 10 in. No. 43 May 1978 4 and 13 0.09 2.12 1.68 4

5 4 in. No. 44 January 1978 4 and 13 0.07 1.30 m

5 3 in. No. 57 Novecer 1977 4 and 13 0.09 4.17 2

18 in. No. 57 July 1977 4 and 13 0.06 9.55 1.59 1

4 24 in. No. 57 September 1976 4 and 13 0.18 25.13 10.59 1

2 (E1. 154.46) 24 in. No. 57 September 1976 4 and 13 0.18 22.54 9.05 1

2 (El. 154.55)

L 8 in. No. 84 February 1977 4 and 13 0.08 1.13 1.01 7

8 f

10 in. No. 90 January 1978 4 and 13 0.07 2.51 1.f7 3

4 I

3 in. No. 92 December 1977 4 and 13 0.05 1.78 1.55 3

3 b

'.:s y.

(U

?. -

t

!=

[

i 1

I A

1 Reported to the nearest 0.01 inch.

2As of July 1985.

IN

~~

~ ~

~ ^ ~ ~

~

(

r TABLE 10 SU MARY OF PENETRATION DIFFERENTIAL SETTLEMENTS REACTOR BUILDING HNP-2 AND REACTOR BUILDING HNP-1 I

Ratio of Differential Measured Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Dates Pipe Anchor Pipe Anchor 8 in. No. 183 January 1978 1 and 29 0.07 0.99 0.53 7

13 8 in. No. 184' December 1977 1 and 29 0.08 3.58 2.30 2

4 f.

[

[-

6 I.:

1 7

5 7

b P

!.S

?

6 3 Reported to the riearest 0.01 inch.

2As of July 1985.

f

- - - - - - - - - - - ~ - - -

F E

i e-t.

l 1.

m-m ib 7

FIGURES e

'l i

l I.,

PT i..

r s.

?

).

1

?

i f

4 0

4 l

l I

y-l l

1

_ LEGEND N

l h BENCHMARM

- F-

~ PENETRATION (Unit 2 only) g M

g28 g2 6T q

i NE

- I NE SE Q

50 10p FT 1

S 6

32 3

REACTOR "1 REACTOR

2 Scale (hNE

~

RADWASTE "2 RADWASTE # 2 1

3 S

NW SW (h NW, 37

@9 10 1

NE SE 1

NE SC i

SE TUR8INE

l CONTROL TUftBINE *2 39 h

Sk NW 2

sW NW 3,

l 1

,i NOTE: Location of benchmarks and penetrations are 1

for reference only. For exact locations and l,

details reference Plant Hatch Procedure i

HNP-2-3425.

E. I. HATCH NUCLEAR PLANT BECHTEL i

i JOB 6511 POWER BLOCK BENCHMARK AND PENETRATION LOCATIONS FIGURE 1

< vy

-r

~y W N

-W M-p-p

~

m fu

, ~-

--v s

4N NE SE NI-S U

W

\\ >> /

=@

rei",'

0FFGAS (MAIN) STACK INTAME STRUCTURE

'rn r E*

LEGEND-NEM /

M /SE a

BENCNMARK PENETRATION O

SO 100 FT E M m Scale 19 20 f K L)SW NW'/

l DIESEL GENERATOR BUILDING l

NOTE: Location cf benchmarks and penetrations are 1

E. I. HATCH NUCLEAR PLANT for reference only. For exact locations and BECHTEL details reference Plant Hatch Procedure HNP-2-3475.

BENCHMARK AND PENETRATION JOB 6511 i

LOCATIONS FOR OFFGAS STACK, INTAKE STRUCTURE AND DIESEL GENERATOR BUILDING FIGURE 2

c-y v

--- m - m ----

M f' E.

I. HATCH NUCLEAR PLANT-SETTLEMENT R EACTO R BUILDING U NIT 1 BENCHMARKS 1.00 0.00 -

O c'

d

~ 1.00 4

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N

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- ^

- 0

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^

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a O

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3

. 3+

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+ F+

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s

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+

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-3.00 1

-4.00

'69 '70 '71 '72 '73 '74 '75 '76 *77 '78 '79 '80'81 '82 '83 '84 '85'86'87 TIM E-YEARS o

SW

+

SE o.

NE a

NW l

E. I. HATCH NUCLEAR PLANT BECHTEL j

NOTE: Approximate time of structure completion i

in May 1976.

8 REACTOR BUILDING UNIT 1 m 65U

{

BENCIMARK SETTLEENT

[i FIGURE 3

.r1

-, c gyT a o.,

7 y 7 %, wm,,--

m---p; w-,5-- ---,y g - g- - g-q E.

I.

HATCH NUCLEAR PLANT-S ETTLEMENT R EACTO R BUILDING UNIT 2 BENCHMARKS 1.00 0.00

=

0

-1.00 g

4 aQhh hb ol g',+

e 3

J 3 o13 sy

-2.00 9

-3.00 t

l

-4.00

'G9'70'71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 TI M E-YEAR S a

SW

+

SE o

NE a

NW E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion i

I" Y

m 65H REACTOR BUILDING UNIT 2 f

BENCHMARK SETTLEENT FIGURE 4

\\) S R

UW 6 :D PTS 7 H

m E.

I.

HATCH NUCLEAR PLANT-SETTLEMENT RADWASTE BUILDINO U N IT 1 BENCHMARKS' 1.00 O.OO l

0 - 1.0 0 -

T 2W

-2.00 9

-3.00 l

l

- 4. O O

'69 '70 '71 '72 '73 '74 '75 '76 '7*/ '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 3

I TI M E-YEARS o

SW

+

SE o

NE a

NW E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion not known.

RADWASTE BUILDING UNIT 1 g

BENCIMARK SETTLEENT lI

-FIGURE 5 f

m O JJ 6

'3 LCY V ' 'Y V' ]

8 M

M M

M M,

]

E.

I.

HATCH NUCLEAR PLANT-SETTLEMENT RADWASTE BUILDING UNIT 2 BENCHMARKS

1. 0 0 D-n

%m DG **

0.00 g"'

gd

$a a

o

>* 4 a 6*

3 e

~ 1.0 0 l

,i 2y

-2.00 2

i

?

-3.00 k

-4.00

'69 '70 '71 '72 '73 '74 '75 '76 '77 '78 '79 '80'81 '82 '83 '84 '85 '86 '87 TI M E-YEARS c

SW

+

SE o

NE a

NW I

I E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion in October 1975.

RADWASTE BUILDING UNIT 2 BENCIMARK SETTLEENT FIGURE 6 l

7... m..a

". - i

^;

f=

j

,] ',q

,q

]

7 rr q a

E.

I.

HATCH NUCLEAR PLANT-SETTLEMENT TURBINE BUILDINO U NIT 1 BENCHMARKS 1.00 0.00 M

o S

'6 4 6

.A

.6 s a sA

' *lmidd*++ e- +

"+ i.,.

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'X

+

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o s

I

)

-3.00 i

i

-4.00 f

'69 '70 '71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 il i

TI M E-YEARS

! I o

SW

+

SE o

NE a

NW E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion in January 1975.

JOB 6511 8

TURBINE BUILDING UNIT 1 BENCHMARK SETTLEENT i

FIGURE 7

.e 3-v7 cr 3

o.y p.y

o. 4 e. 9 g

r m,,

_q

.y y

q

.~

E.

I.

HATCH NUCLEAR P LANT-S ETTLEM.e1N T TURBINE BUILDING UNIT 2 BENCHMARKS 1.00 0.00 N

'MQ MD("

!G

-1.00 T

2y

-2.00

!il

-3.00

-4.00

~

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SW

+

SE o

NE a

NW f

E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion JOB 6511 in May 1976.

TURBINE BUILDING UNIT 2 BENCHMARK SETTLEMENT FIGURE 8

1 r-1 4

.t

q

. i i

E.

I.

HATCH NUCLEAR PLANT-S ETTLEMriNT CONTROL BUILDINO BENCHMARKS 1.00 i

O.00 i:

d

% b. afM

_1M io i A i

I 3a ia ia ia 4 i

_1,00 a

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'69 '70 '71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 TI M E-YEARS c

SW

+

SE o

NE a

NW l

[t E. I. HATCH NUCLEAR PLANT BECHTEL

[

NOTE: Approximate time of structure completion i

in January 1975.

JOB 6511

[

CONTROL BUILDING BENCHNARK SETTLEENT FIGURE 9 j-e

3.. m y n-r g

. =,

,m

.,. g.v 3. g 2j f.,y

, 3 p

.q E.

I.

HATCH NU CLE AR PLANT-SETTLEMENT DIESEL GEN ERATOR BUILDING BENCHMARKS 1 00 0.00

~-

I doo 1

a "A

" S-5

-'i l

Q 4

I a s

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ig "O

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l' I

I

-4.00 l

'69 '70 *71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 i

TI M E-YEARS i

a SW

+

SE o

NE a

NW I

I I

E. I. HATCH NUCLEAR PLANT BECHTEL e

NOTE: Approximate time of structure completion f

in January 1975.

JOB 6511 DIESEL GENERATOR BUILDING BENCHMARK SETTLEMENT FIGURE 10

.ca 0

-v v

v v

N tr - ]

v7

+

,3 1

y gg q)).

3

.] ' ]

[

v e';~+

E.

I.

HATCH NUCLEAR PLANT-SETTLEME T

^

4.00 0.00

=

t N

-1.00 T

I n"'E@ @@ ge,a$ 3@

h

+

3Ey

-2.00 E

I

-3.00 i

i I

I I

-4.00 I

'69 '70 '71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '8 4 '85 '8 6 *B7 TI M E-YEA RS o

SW

+

SE o.

NE a

NW E. I. HATCH NUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion j

in October 1974.

JOB 6511 INTAKE STRUCTURE I

BENCIMARK SETTLEENT l

FIGURE 11 l

.r - 3,, y t r ~,c m r v ~

> v u s>

i 4

y 3

4 p,

_. 3

,.3 E.

I.

HATCH NUCLEAR PLANT-S ETTLEMENT OFFOAS STACK BENCHMARKS 1.00 0.00 2

Y

[ @i3

@9 0

D pS is 3 ijit e

b ~ 1.00 s

1 2y

-2.00 o

2

-3.00 i

l 1

-4.00 I

'69'70'71 '72 '73 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 TI M E-YEARS c3 S

+

W o

NE E. I. HATCH NOCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion in October 1974.

JOB 6511 l

OFFGAS (MAIN) STACK BENCHMARK SETTLEMENT i

i FIGURE 12

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s' APPENDIX A T

TECHNICAL SPECIFICATION 3l4.7.8 n

SETTLEMENT OF CLASS 1 STRUCTURES

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PLANT SYSTEMS 3/4.7.8 SEITLEMENT OF CLASS 1 STRUCTURES.

l LIMITING CONDITION FOR OPERATION 3.7.8 The total settlement of each Class I structure or the differential settlement between or across Class I structures shall not exceed the allowable values of Table 3.7.8-1.

y s

APPLICABILITY: All CONDITIONS.

ACTION:

a.

With either the total settlement of any structure or the dif-ferential settlement of any structures exceeding 75% of the allowable settlement value, conduct an engineering review of field conditions and evaluate the consequences of additional settlement. Submit a special report to the Commission pur-suant to Specification 6.9.2 within 60 days, containing the.

results of the investigation, the evaluation of existing and possible continued settlement and the remedial action to be taken, if any, including the date of the next survey.

b.

With the total settlement of any structure or the differenti.a1 settlement of any structures exceeding the, allowable settlement 9

value of Table 3.7.8-1, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l SURVEILLANCE REQUIREMEsTS 1

4.7.8 The total settlement of each Class I structure'or the dif-ferential settlement'between Class I structures listed in Table 3.7.8-1 shall be determined to the nearest 0.01 foot by measurement and calcula-tion:

a.

At least once per 31 days;

)'

1.

During the first 6 months of unit operation, 2.

Until observed settlement has stabilized,* and 3.

Whenever previously stabilized

settlement exceeds O.10 inch since the previous reading.

b.

At least once per 6 months.

s0.10 inch from previous reading.

HATCH - UNIT 2 3/4 7-31

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ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES

-4 m

Z Allowable Allowable e

Total Differential ~

Settlement settlement E

Structure fInchest fInchest Reactor Building 1s.5 90 Control Building 2.5 Diesel Cenerator Building 2.5 Main Stack 2.5 intake Structure 2.5 s

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io be established and reported to the Commission by November 1, 1978.

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es Oh APPENDIX B "Y'

i.

SETTLEMENT DATA e

REACTOR BUILDING. UNITS 1 AND 2 e*

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e j ADDITIONAL COMMENTS TO APPENDICES B THROUGH F J

AS A RESULT OF NRC QUESTIONS

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APPENDIX B 1.

Item #6 of Section B: Northwest should be northeast.

2.

Add the following to Section C:

(2) o Original elevations of ben,chmarks is based on settlement i

given on Figure 2A-16A, Sheet 2, Amendment 35, 7/77.

(3) o Asettlementmarker(benchmark)changewasmadefor the northwest marker in October 1977.

It was assumed, that no movement of the marker occurred since the previous reading. An adjustment was made to the ref-erence elevation to account for the previous movement.

APPENDIX F i

i 1.

Add the following to Section C:

(5) o Based on correspondence, it was concluded that the ref-erence elevations for each benchmark was changed in January 1975.

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APPENDIX B SETTLEMENT DATA REACTOR BUILDING UNITS 1 AND 2 NOTES A.

GENERAL 1.

All reference elevations and survey readings are in feet.

2.

All delta (movement) values are in inches.

y 3.

For the delta values, + indicates heave and - indicates settle-ment.

~

99 4.

For each structure, settlement markers and settlement benchmarks are used interchangably.~They are not to be confused with the reference benchmarks used for elevation control, shown on Figure N

13.~~

L r-B.

REACTOR BUILDING UNIT 1 1.

Assumed a "zero" date for the beginning of settlement monitoring in March 1969.

r 1

2.

Settlement values for the southwest marker, between December 1969 and July 1970, were estimated from Figure 2A-16, sheet 1 of the r".

Unit 2 FSAR, Amendment 35, issued in July 1977. No settlement J,*

data for the remaining markers were available in this time frame.

The settlement values in 1974, for all four markers were estimated 3.

from the same figure as in item 2 above.

4.

The January 1975 reading for the northwest marker was changed from 0.079 feet to 0.179 feet.

5.

A settlement marker (benchmark) change was made for the northwest marker in November 1977.

It was assumed that no movement of the marker occurred between November 1977 and the previous reading, a'

July 1977. An adjustment was then made to the reference elevation to account for the previous movement.

i IT Li 6.

New settlement markers (ber..hmarks) were established in January 1980forthesouthwest,southeastandnorth(6tmarkers. The y

reference elevations were adjusted to account for the previous movement.

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7.

The January 1981 reading for the southwest marker (benchmark) wis taken on the "old' marker. The reference elevation was c langed to account for this. Subsequent readings use the marker established in January 1980.

C.

REACTOR BUILDING UNIT 2 1.

Assumed a "zero" date for the beginning of settlement monitoring in July 1972. This is based on notes appearing on Figure 2A-16, j

sheet 1, of the Unit 2 FSAR, Amendment 35, issued in July 1977..

)

2.

A settlement marker (benchmark) change was made for the southeast marker in April 1978.

It was assumed that no movement of the marker occurred between April 1978 and the previous reading, February 1978. An adjustment was then made to the reference ele-vation to account for the previous movement.

3.

New settlement markers (benchmarks) were established in January 1980 for the southwest and northeast markers. The reference elevations were adjusted to account for the previous movement.

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APPENDIX C SETTLEMENT DATA RADWASTE BUILDING. UNITS 1 AND 2 O
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APPENDIX C g
SETTLEMENT DATA RADWASTE BUILDING UNITS 1 AND 2 NOTES A.
GENERAL 2.
1.
All reference elevations and survey readings are in feet.
y, 2.
All delta (movement) values are in inches.
+
3.
For the delta values, + indicates heave and - indicates settle-ment.
4.
For each structure, settlement narkers and settlement benchmarks are used interchangably. They are not to be confus-d with the reference benchmarks used for elevation control, shown on Figure a
13.
n B.
RADWASTE BUILDING UNIT 1 1.
Assumed a "zero" date for the beginning of settlement monitoring in January 1972. This is based on Figure 2A-16, sheet 2, of the Unit 2 FSAR, Amendment 35, issued in July 1977.
r 2.
New settlement markers (benchmarks) were established in July 1978 for each marker. The reference elevations were adjusted to account for the previous movement.
~
C.
RADWASTE BUILDING UNIT 2 1.
Assumed a "zero" date for the beginning of settlement monitoring in October 1975. This is based on Figure 2A-16A, sheet 5, of the Unit 2 FSAR, Amendment 35, issued in July 1977.
2.
'All survey readings from October 1975 to March 1977 were estimated from figure referenced in item 1 above.
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F, dPPENDIXD no SETTLEMENT DATA TURBINE BUILDING UNITS 1 AND 2 b.
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APPENDIX D
\\-
SETTLEMENT DATA
(
TURBINE BUILDING UNITS 1 AND 2 m
NOTES a.
m A.
GENERAL 1.
All reference elevations and survey readings are in feet.
le 2.
All delta (movement) values are in inches.
3.
For the delta values, + indicates heave and - indicates settle-ment.
~
4.
For each structure, settlement markers and settlement benchmarks are used interchangably. They are not to be confused with the reference benchmarks used for elevation control, shown on Figure 13.
P B.
TURBINE BUILDING UNIT 1 1.
Assumed a "zero" date for the beginning of settlement monitoring in January 1972.
2.
The reported survey reading for the southeast marker in' July 1978 6
was 111.926 feet. Based on previous and subsequent readings this was assumed to be incorrect. Changed survey reading to 111.826 feet.
3.
New settlement markers (benchmarks) were established in July 1978 for the northwest, northeast and southeast markers. The reference 2-elevations were adjusted to account for the previous movement.
4.
A new settlement marker (benchmark) was established in June 1979 for the southwest marker. However, no readings have been taken due to high radiation.
C.
TURBINE BUILDING UPIT 2 1.
New settlement markers (benchmarks) were established in May 1977 for each marker.
It was assumed that no movement of the markers occurred between May 1977 and the previous reading, April 1977.
An adjustment was then made to the reference elevation to account for the previous movement.
1 e-
f 2.
/ new settlement marker (benchmark) was established in June 1977 F-for the northeast marker.
It was assumed that no movement of
~ pe marker took place between June 1977 and the previous reading, my 1977. An adjustment was then made to the reference elevation to account for the previous movement.
3.
The northeast marker (benchmark) was destroyed in March 1978. A lF new marker was established in April 1978.
It was assumed that no movement occurred between April 1978 and the previous reading, February 1978. An adjustment was then made to the reference ele-vation to account for the previous movement.
m 4.
No survey readings have been taken on the northwest marker (bench-mark) since January 1979 due to high radiation.
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' APPENDIX E Y
6 SETTLEENT DATA
-r*
b*
CONTROL BUILDING AND DIES,EL GENERATOR BUILDING P
i.
'I.
+
F 'i e'
r-
.4.
i Fs
?.
g.
a b
f, h
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_ _ _.... ~
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F Y
APPENDIX E l
SETTLEMENT DATA CONTROL BUILDING AND DIESEL GENERATOR BUILDING e
NOTES fe A.
GENERAL 1.
All reference elevations and survey readings are in feet.
2.
All delta (movement) values are in inches.
3.
For the delta values, + indicates heave and - indicates settle-ment.
4.
For each structure, settlement markers and settlement benchmarks y
are used ir.terchangably. They are not to be confused with the reference benchmarks used for elevation control, shown on Figure 7,
13.
B.
CONTROL BUILDING F
k 1.
Assumed a "zero" date for the beginning of settlement monitoring in January 1972.
~
2.
The settlement values for all four markers (benchmarks) in 1974 A
were estimated from Figure 2A-16A, sheet 1, of the Unit 2 FSAR, Amendment 35, issued in July 1977.
3.
New settlement markers (benchmarks) were established in July 1978 for each marker. The reference elevations were adjusted to account p
for the previous movement.
)
C.
DIESEL GENERATOR BUILDING 1.
Assumed a "zero" date for the southeast and southwest markers (benchmarks) for the beginning of settlement monitoring in December 1972. This is based on Figure 2A-16A, sheet 3, of the a
Unit 2 FSAR, Amendment 35, issued in July 1977. No "zero" dates could be established for the northwest ar ' northeast markers.
2.
The settlement values in 1974 for all four markers (benchmarks) 6 were estimated from the above referenced figure in item 1.
7
F F
f
'Wew settlement markers (benchmarks) were established for each 3.
narker in October 1977.
It was assumed that no movement occurred between the October 1977 reading and the previous reading, July 1977. An adjustment was then made to the reference elevation to account for the previous movement.
C
'[,
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'PPENDIX F A
e de SETTLEMENT DATA v
u-INTAKESTRUCTUREANDO7 GAS (MAIN) STACK L.
M 7.
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APPENDIX F SETTLEMENT DATA f
INTAKE STRUCTURE AND OFFGAS (MAIN) STACK
{
NOTES A.
GENERAL
~
1.
All reference elevations and survey readings are in feet.
2.
All delta (movement) values are in inches.
fo 3.
For the delta values, + indicates heave and - indicates settle-
[.
ment.
4.
For each structure, settlement markers and settlement benchmarks
(,a are used interchangably. They are not to be confused with the reference benchmarks used for elevation control, shown on Figure 13.
I:
B.
INTAKE STRUCTURE
(
1.
Assumed a "zero" date for the beginning of settlement monitoring in July 1972.
f' 2.
No survey readings are available between July 1972 and July 1978.
L.
GPC correspondence indicates that the structure settled about 0.1 foot.
fl 3.
New settlement markers (benchmarks) were established in July 1978, for each marker. The reference elevations were adjusted to account for the estimated previous movement of 0.1 foot.
,r u
C.
OFFGAS(MAIN) STACK 1.
Assumed a "zero" date for the beginning of settlement monitoring in September 1971.
T, 2.
Between September 1971 and April 1972 more than one survey reading L
was taken in certain months.
The reported reading here is an average of those readings for a particular month.
P 3.
New settlement markers (benchmarks) were established in January 1973 for each marker.
It was assumed that no movement occurred between January 1973 and the previous reading, July 1972. The f
refere.nce elevations were adjusted to account for the previous a
movement.
m
!!j 1
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F E
f'
4. Jil settlement values in 1974 for each marker were estimated from Figure 2A-16A, sheet 4, of the Unit 2 FSAR, Amendment 35, issued in July 1977.
Ti.
5.
It was assumed that the February, March and April 1975 survey readings for the south marker (benchmark) were reported incor-rectly. The readings were changed from 119.891, 119.890 and 119.891 feet to 119.981, 119.980 and 119.981 feet.
6.
Anewsettlementmarker(benchmark)wasestablishedforthesouth marker in May 1975.
It was assumed that no movement occurred f;
between the May 1979 and the previous reading, April 1975. The reference elevation was adjusted to account for the previous movement.
7.
It was assumed that the January 1976 survey reading for the south marker (benchmark) was reported incorrectly. The reading was changed from 119.997 feet to 119.979 feet.
C b.
8.
New settlement markers (benchmarks) were established for each marker in January 1980. The reference elevations were adjusted i
to account for previous movement.
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ENCLOSURE 2 9
._.. ~ ; *..
4 i
. y.t.,
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.l ht u,.
Jyt 2 91986 Mr. P. R. Bemis M
Georgia Power Company 333 Piedmont Avenue 14th Floor. Nuclear Operations Atlanta, Georgia 30308 f
E. I. Hatch Nuclear Plant Units 1 & 2 f
Bechtel Job'6511 - 034 - R66720 REA RESPONSE LETTER Request for Engineering Assistance REA - HT-66720. EVALUATION OF BUILDING i
SETTLEMENT DATA File: A29.3/A35.1/0110/A57.75 B-GP-14504 l
Dear Mr. Bemis:
In response to your request in the subject REA, we have completed our review and evaluation of the January, 1986 settlement data. Enclosed (see attachment A) are Tables 1 through 10 and Figures 3 through 12 of the " Report on Settlement l
of Major Plant Structures "(Ref.B-GP-14384 dated June 16,1986) which have been
[
updated to reflect changes resulting from the January 1986 data.
In summary, all structures reviewed are performing as they have in the past. No total settlements have reached'the preaicted values, and all differential settlements are less than their corresponding allowable. However, we should point out that, six markers (all four in the Diesel Generator Building and the Northeast Marker in each Reactor Building) recorded movements exceeding 0.10 i
inches from the previous survey of J;ly 1985. While the Individual marker in the case of the Reactor Building excreded the 0.10 inch criterion, the average settlement for the structure did not exceed the Technical Specification re-survey requirement. Consequently, a re-survey of the Reactor Building markers was not required (viz, by interpretation of Technical Specification Section 4.7.8).
The markers for the Diesel Generator Building, however, were re-surveyed to confirm the validity of the data.
Finally, the January 1986 settlement data shows no notable departure from the historical settlement information available, and serves to re-affirm the conclusions and reco.unendations in the referenced report.
Also enclosed (see attachment B) are corrections to Tables 1, 3, and 4 (previously issued based on the July 1985 data) of the referenced report.
Please note that these tables have been superseded by the updated tables contained in Attachment A and are included for information only.
Please update your copy of the referenced report accordingly, i
__........._.___..._.._..m_t.,__w,_.
lJ'Ji. E E 1986 Mr.P.R.Bem{s 2
B-GP-1450' r
i With regard to your request to develop personal computer software to compute building differential settlement, the work is well underway and is forecast to be complete in early August.
If you have any question on require additional information concerning the matter, please do not hesitate to contact us.
Very truly yours, Driginal signed by E
JUL 2 9 1986 Gaffo. A. A.csIKosi ur Project Engineer GAK:CLW:SJ0:blf Enclosures Attachment A (20 sheets)
Attachment B ( 3 Sheets) cc: Southern Company Services, Inc.
bec:
J. Lydard, w/1 W. F. Garner, w/l K. khianey,t;/1 W. L. Orr, w/l C. L. Weaver, w/1 Georgia Power Company (Atl)
A. Sanver, w/1
v. R. Jordan, w/1 M. Lewis, w/1 L. T. Gucwa, w/l R. S. Nadolski, w/1 Disk CIVIL 8 M. J. Blackwood, w/1 R. D. Baker, w/l Georgia Power Company (HNP)
H. C. Nix, Jr., w/l S. Tipps, w/o I
l 9e
4
-ATTACHMENT A TO B-GP-14504 f
(20 SHEETS)
I Y
l l
l f
)
l l
i L
L l
f i
1 l
r Se
l TABLE 1 PREDICTED AND MEASURED TOTAL SETTLEMENTS l
I.
1
[
RATIO OF MEASURED SETTLEMENT-INCHES 2 TO PREDICTED-%
MEASURED STRUCTURE PREDICTED MAXIMUM TO DATEz MAXIMUM TO DATE8 I
l Reactor Building Unit 1 3.1 2.8 2.7 90 87 Reactor Building Unit 2 4.5 2.0 1.3 44 40 Turbine Building Unit 1 1.5 1.2 1.1 80 73 Turbine Building Unit 2 2.0 0.3 j
15 Radwaste Building Unit 1
1. 5 0.8 0.7 53 47 l
Radwaste Building Unit 2 3.5 0.5 0.1 14 3
Control Building
2. 0 1.5 1.5 75 75 Diesel Generator Building 2.0
1. 0
. D. 8 50 40 Offgas (Main) Stack 2.0 0.4
0. 4 20 20
, Intake Structure 2.0 1.54 1.54 70 75 i
l l
1 l
[
l l
i 3 Settlements are reported to the nearest 0.1 inch.
2*anuari1986 reading.
8A11 measurements are currently indicating heave.
4 Measured settlements are estimates only, since complete records do not exist prior to July 1978.
,, y TABLE 2
SUMMARY
OF DIFFERENTIAL SETTLEMENTS ACROSS STRUCTURES
..l.
I t
DIFFERENTIAL RATIO OF BETWEEN SETTLEMENT MEASURED REFERENCE DIRECTION BENCHMARK INCHES 2 TO ALLOWABLE STRUCTURE DATE OF TILT NUM8ERS1 ALLOWABLE MEASURED 3 PERCENT Reactor 5-76 N-S 1 and 2 0.40 0.05 13 Building N-S 3 and 4 0.41 0.06 15 Unit No. 2 E-W 1 and 3 1.67 0.18 11 i
E-W 2 and 4 1.61 0.07 4
Radwaste 10-75 N-S 5 and 6 1.85 0.37 20 Building N-S 7 and 8 1.92 0.31 16 Unit No. 2 E-W 5 and 7 1.58 0.02 1
E-W 6 and 8
0. 96
0. 04 4
Control 1-75 N-S 9 and 10 1.00 0.16 16 Building N-S 11 and 12
0. 95
0. 24 25 E-W 9 and 11 3.01 0.24 8
E-W 10 and 12 3.46 0.16 5
Turbine 5-76 N-S 13 and 14 2.59
0. 23 9
Building N-S 154 and 16 2.46
0. 30 12 Unit No. 2 E-W 13 and 154 2.96
0. 18 6
E-W 14 and.16 3.37
0. 11 3
Diesel 1-75 N-S 17 and 18 5.09 0.14 3
Generator N-S 19 and 20 4.73
0. 24 5
Building E-W 17 and 19 2.47
0. 43 17 E-W 18 and 20 2.47
0. 05 2
Offgas 10-74 N-S 21 and 22 0.44 0.14 32 (Main)
E-W 21 and 23 0.55 0.08 15 Stack E-W 22 and 23 0.50 0.06 12 Intake 10-745 N-S 24 and 25 2.50 0.20 0
Structure N-S 26 and 27 2.50 0.07 3
E-W 24 and 26 0.65 0.01 2
E-W 25 and 27 1.25 0.12 10 2 Refer to Figure 1 for benchmark. identification.
2 Reported to the nearest 0.01 inch.
3As of January 1986.
4No current survey data are available for benchmark 15; used last available data, January 1979.
sActual benchmarks used were established in July 1978.
l i
TABLE 3
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS
. j-REACTOR BUILDING HNP-2 AND SOIL Ratio of Differential Measured i
Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 8 in. No. 1 November 1977 1
0.01 0.73 1.03 1
1 10 in. No. 2 December 1977 1
0.01-1.22 0.96 1
1 18 in. No. 3 April 1978 1
0.0 1.26 0.72 0
0 0.04 1.26 0.72 3
6 18 in. No. 4 March 1978 1
6 in. No. 8 November 1977 1
0.01 1.22 0.75 1
1 10 in. No. 10 January 1978 2
0.11 1.22 0.96 9
11 18 in. No. 11 March 1978 2
0.13 1.26 0.72 10 18 20 in. No. 12 January 1978 2
0.11 1.13 0.56 10 20 18 in. No. 13 April 1978 2
0.13 1.26 0.72,
10 18 14 in. No. 24 November 1977 2
0.11 1.15 1.06 10 10 10 in. No. 41 February 1977 2
0.02 1.28 0.88 2
2 16 in. No. 42 March 1978 2
0.13 1.06 0.73 12 18 14 in. No. 134 March 1978 1
0.04 1.15' 1.13 3
4 20 in. No. 161 January 1978 1
0.0 1.13 0.71 0
0 I
~
3 Reported to the nearest 0.01 inch.
2As of January 1986.
i
TABLE 4
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS j,
DIESEL GENERATOR BUILDING AND SOIL Ratio of Differential Measured Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Panetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 6 in.
January 1978 17 0.02 0.57 0.57 4
4 10 in.
December 1971 17 0.353 0.92 38 d
b 4
s 3 Reported to the nearest 0.01 inch.
2As of January 1986.~
sEarliest reading on Benchmark 17 is December 1972.
em -
TABLE 5
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS j,
MAIN STACK AND SOIL i
~
Differential Ratio of Settlement - Inches -
Neasured 1
Measured Allowable to Allowable Penetration Installation Benchmark to Date2 in Pipe Percent 18 in.
June 1974 23 0.10 0.45 22 12 in.
May 1974 23 0.10 0.45 22 20 in.
June 1974 22 0.04 0.46 9
6 in.
May 1974 22 0.04 0.46 9
t i
2 Reported to the nearest 0.01 inch.
2As of January 1986.
\\
mr
--,m_--
TABLE 6
SUMMARY
OF PENETRATION OIFFERENTIAL SETTLEMENTS g,
INTAKE STRUCTURE AND SOIL f
Ratio of Differential Measured Settlement - Inches 1 to Allowable Date of Nearest Measured Allowable 3 Percent Penetration Installation Benchmark to Date2 Pipe Support Pipe Support 30 in.
January 1978 25 0.29 1.38 0.66 21 44 El. 97.28 ft 12 in.
July 1974 25 0.29 0.99 1.19 29 24 18 in.
(Unit 2)
February 1978 25 O.29 2.78 2.03 10 14 30 in.
January 1978 25 0.29 1.38 0.66 21 44 El. 91.75 ft.
(Unit 1) 30 in.
January 1978 25 0.29 1.38 0.66 21 44 El. 91.75 ft.
(Unit 2) 18 in.
February 1978 27 0.17 2.47 1.27.
7 13 (Unit 1) 6 in.
April 1976 26 0.10 1.50 0.94 7
11 i
2Reportedtokhenearest0.01 inch.
2 Measured differential settlements are estimates only, since complete records do not exist prior to July 1978.
Measured settlements are as of January 1986.
8 Allowable settlement is based on both pipe stress and support loads.
l l
TABLE 7
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS i
qEACTORBUILDINGHNP-2ANDRADWASTEBUILDINGHNP-2 l
Ratio of Differential Measured Settlement - Inchest to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Daten Pipe Anchor Pipe Anchor 1 in. No. 51 October 1977 2 and 5 0.16 1.54 10 6 in. No. 51 October 1977 2 and 5 0.16 1.14 14 1.5 in. No. 102 November 1977 2 and 5 0.14 1.07 13 8 in. No. 153 February 1977 4 and 5 '
O.12 1.48 0.88 8
14 s
2 Reported to the nea' rest 0.01 inch.
2As of January 1986.
TABLE 8
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS
{
REACTOR BUILDING HNP-2 AND CONTROL BUILDING l
Ratio of Differential Measured Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 24 in. No.,59 May 1978 3 and 10 0.14 26.03 13.23 1
1 3 in. No. 60 January 1978 3 and 10 0.23 1.48 0.62 16 37 18 in. No. 61 August 1977 3 and 10 0.24 9.55 1.86 3
13 24 in. No. 61 September 1976 3 and 10' O.17 12.14 5.06 1
3 4 in. No. 68 January 1978 3 and 10 0.23 1.84 0.85 13 27 4 in. No. 69 January 1978 3 and 10 0.23 1.99 0.78 12 29 4
1 r;
2 Reported to the nea' rest 0.01 inch.
2As of January 1986.
TABLE 9
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS fEACTORBUILDINGHNP-2ANDTURBINEBUILDINGHNP-2 l
Ratio of Differential Measured Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent P::netration Installation Benchmark to Oate2 Pipe Anchor Pipe Anchor 10 in. No. 43 May 1978 4 and 13 0.01 2.12 1.68 1
1 4 in. No. 44 January 1978 4 and 13 0.01 1.30 1
3 in. No. 57 November 1977 4 and 13 0.01 4.I7 1
18 in. No. 57 July 1977 4 and 13 '
O.14 9.55 1.59 1
9 24 in. No. 57 September 1976 4 and 13 0.26 25.13 10.59 1
2 (El. 154.46) 24 in. No. 57 September 1976 4 and 13 0.26 22.54 9.05
,1 3
(El. 154.55) 8 in. No. 84 February 1977 4 and 13 0.17 1.13 1.01 15 17
~
10 in. No. 90 January 1978 4 and 13 0.01 2.51 1.77.
I 1
3 in. No. 92 December 1977 4 and 13 0.04 1.78 1.55 2
3 1.
2 Reported to the nearest 0.01 inch.
2As of January 1986.
w
TABLE 10
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS lREACTORBUILDINGHNP-2ANDREACTORBUILDINGHNP-1 Ratio of Differential Measured i
Settlement - Inches 1 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Date2 Pipe Anchor Pipe Anchor 8 in. No. 183 January 1978 1 and 29 0.11 0.99 0.53 11 21 8 in. No. 184 December 1977 1 and 29 0.12 3.58 2.30 3
5 I ".
1 Reported to the nearest 0.01 inch.
2As of January 1986.
1
1 1
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HATCH NU CLE AR PLANT s'
R EACTO R BUILDING U N IT 1 BENCHMARKS i
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l E. I. MATCH NUCLEAR PLANT BECHTEL 1
i NOTE: Approximate time of structure completion m 65H i
in May 1976.
REACTOR SUILDING UNIT 1 l
BENCWARK SETTLEE NT FIGURE 3 i
j 1
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=
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+
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RADWASTE BUILDING UNIT 1 BENCHMARK SETTLEE NT FIGURE 5
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HATCH NU CLE AR P LA NT-S ETTLE M ENT RADWASTE BUILDING U N IT 2 BENCHMARKS 1.00 w-y e
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+
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NW E. I. HATCH MUCLEAR PLANT BECHTEL NOTE: Approximate time of structure completion JOB 6511 in October 1975.
RADWASTE BUILDING UNIT 2 KKMARK SETTLEENT FIGURE 6
L 1
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NOTE: Approximate time of structure completion JOB 6511 in May 1976.
TUR8INE BUILDING UNIT 2 i
BEKMARK SETTLEENT FIGURE 8 I
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H ATCI-I NU CLE AR P LANT-S ETTLEMENT INTA K E STRUCTURE BENOHMARKS O.00 1
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E. I. HATCH NUCLEAR PUWT BECHTEL NOTE: Approximate time of structure completion JOB 6511 in October 1974.
3, g gg BENCMARK SETTLEENT FIGURE 11 0 9
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HATCH N U C LE AR PLANT-S ETTLE M ENT OFFOAS STACK SENCHMARKS 1.00 v=-
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'69 '7o '71 '72 '73 *7'4 '75 '76 '77 '78 '79 '80,*s1 TIME-YEARS c
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NE E. I. HATCH NUCLEAR PLANT KCHTEL NOTE: Approximate time of structure completion 65H in October 1974.
OFTGAS (MRIN) STACK K EHMARK SETTLEMENT FIGURE 12 4
O k
e ATTACHMENT B TO B-GP-14504
( 3 SHEETS) e e@
TABLE 1 0
PREDICTED AND MEASURED TOTAL SETTLEMENTS tj RATIO OF MEASURED i
)
SETTLEMENT-INCHES 1 TO PREDICTED-%
MEASURED STRUCTURE PREDICTED MAXIMUM TO F MAXIMUM TO DATE2 Reactor Building Unit 1 3.1 2.8 2.6 90 84 R; actor Building Unit 2
4. 5 2.0 1.7 44 38 Turbine Building Unit 1 1.5 1.2 1.2 80 80 Turbine Building Unit 2 2.0 0.3 l
15 Radwaste Building Unit 1 1.5
0. 8 0.6 53 40
$ 0.1 14 5
Radwaste Building Unit 2 3.5 0.5 Control Building 2.0
,1. 5 1.5 75 75 Diesel Generator Building 2.0 1.0 1.0 50 50 Offgas (Main) Stack 2.0 0.4 0.3 20 15 r31 16 1.5 Q
Intake Structure
2. 0 1.44 70 l
l l
l I
l 2 Settlements are reported to the, nearest 0.1 inch.
2 July 1985 reading.
8A11 measurements are currently indicating heave.
4 Measured settlements are estimates only, since complete records do not oxist prior to July 1978.
n-
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TABLE 3
SUMMARY
0F PENETRATION DIFFERENTIAL SETTLEMENTS e:
REACTOR BUILDING HNP-2 AND SOIL l
Ratio of Differential Peasured Settlement - Inchess to' Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Dates Pipe Anchor Pipe Anchor
[O 8 in. No. 1 November 1977 1
0.13 0.73 1.03 10 in. No. 2 December 1977 1
0.11 1.22 0.96 9
11 18 in. No. 3 April 1978 1
0.12 1.26 0.72 10 17 0.16 1.26 0.72 13 22 18 in. No. 4 March 1978 1
6 in. No. 8 November 1977 1
0.13 1.22 0.75 11 17 10 in. No. 10 January 1978 2
0.18 1.22 0.96 15 19 18 in. No. 11 March 1978 2
0.20 1.26 0.72 16 28 20 in. No. 12 January 1978 2
0.18 1.13 0.56 16 32 18 in. No. 13 April 1978 2
0.20 1.26 0.72 16 28 14 in. No. 24 November 1977 2
0.18 1.15 1.06 16 17 10 in. No. 41 February 1977 2
0.10 1.28 0.88 8
11 IG in. No. 42 March 1978 2
0.20 1.06 0.73 19 27 14 in. No. 134 March 1978 1
0.16 1.15i 1.13 14 14 20 in. No. 161 January 1978
,1 0.12 1.13 0.71 11 17 3 Reported to the nearest 0.01 inch.
2As of July 1985.
(-
TABLE 4
SUMMARY
OF PENETRATION DIFFERENTIAL SETTLEMENTS DIESEL GENERATOR BUILDING AND SOIL l-l Ratio of Differential Measured Settlement - Inches 2 to Allowable Date of Nearest Measured Allowable Percent Penetration Installation Benchmark to Dates Pipe Anchor Pipa Anchor 6 in.
January 1978 17 0.20 0.57 0.57 35 35
[
10 in.
December 1971 17 c.%
3 0.92 F
A 3 Reported to the nearest 0.01 inch.
2As of July 1985.
8 Earliest reading on' Benchmark 17 is December 1972.
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ENCLOSURE 3 h~
ATTENDANCE LIST s
OCTOBER 21, 1986 MEETING WITH GPC TO DISCUSS HATCH 2 BUILDING SETTLEMENT DATA NAME ORGANIZATION G. Rivenbark NRC/NRR C. P.. Tan.
NRC/NRR J. Heidt GPC 1
M. Lewis Bechtel
'l C. Weaver Bechtel i
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v t e Letter Sequence Other
TAC:11158, (Approved, Closed)
Initiation Request, Request, Request, Request, Request Acceptance... Supplement Administration Meeting, Meeting, Meeting Questions 31 August 1979 27 November 1979 Answers Results Approval, Approval Other: ML19207B486, ML19209C452, ML19253A347, ML19261B636, ML19282C667, ML19283B681, ML20065J906, ML20065K102, ML20083D703, ML20084J700, ML20150F079, ML20207L458, ML20212J238, ML20237G823
MONTHYEAR1979-08-31 [Table View]

ML20212J238

Text

10.0 CONCLUSION

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1.0 INTRODUCTION

10.0 CONCLUSION

10.0 CONCLUSION

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Dear Mr. Bemis: