Text

Forwards Revised Rept on Reanalysis of Safety-Related Piping Sys in Response to 790313 Order.All Mods Will Be Completed by 800201
	ML18136A394
Person / Time
Site:	Surry
Issue date:	01/15/1980
From:	Spencer W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton; Office of Nuclear Reactor Regulation
Shared Package
ML18136A395	List: ML18136A394; ML19257B874;
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	048, 48, NUDOCS 8001210121
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SURRY POWER STATION, UNIT 1 REVISED REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS SURRY POWER STATION, UNIT 1 VIRGINIA ELECTRIC AND POWER COMPANY January 1980 Stone & Webster Engineering Corporation Boston, Massachusetts

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VIRGINIA ELECTRIC AN'D POWER COMPANY, RICHMOND, VIRGINIA 23261 January 15, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Denton:

Serial No. 048 PSE&C/CMRjr:mac:wang Docket No. 50-280 License No. DPR-32 COMPLETION OF SHOW CAUSE ORDER REANALYSIS SURRY POWER STATION UNIT l The Virginia Electric and Power Company letter of December 21, 1979 (Serial No. 1158) gave notification of the completion of analysis associated with the 60 day time period designated in the Nuclear Regulatory Commission Order of August 22, 1979.

The purpose of this letter is to transmit the results of that analysis in a format similar to our previous reports of June 5 and August 1, 1979.

As stated in our December 21, 1979 letter, all modifications associated with the Order of August 22, 1979 will be completed by February 1, 1980.

The attached report concludes our detailed submittals on the design basis earthquake analysis associated with the March 13, 1979 Order to Show Cause for Unit 1.

We will notify you when these modifications are completed.

If you have any questions, please contact us.

~yours, W.

. Spencer Vice President - Power Station Engineering and Construction Services Attachment cc: Mr. Victor Stello, Director Office of Inspection & Enforcement Mr. James P. 0 1Reilly, Director Office of Inspection and Enforcement Region II

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I Section 1

2 3

A B

Table 2-1 2-2 2-3 2-4 3-lA 3-lB 3-2 SURRY POWER STATION, UNIT l TABLE OF CONTENTS INTRODUCTION PIPE STRESS RESULTS..

PIPE SUPPORT RESULTS APPENDIX CROSS REFERENCE OF MKS, FM, FP, PROBLEM N0.

1 SYSTEM CORRESPONDENCE LIST OF TABLES Pipe Stress Reevaluation Summary Nozzle and Penetration Summary Pipe Stress Hardware Modification Summary Hardware Modification Summary Due to Nozzles and Penetration Loading Pipe Support Summary Inside Containment Pipe Support Summary Outside Containment Pipe Support Hardware Modification Summary i

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I SURRY POWER STATION, UNIT 1 SECTION 1 INTRODUCTION The Nuclear Regulatory Commission (NRC) Order to Show Cause of March 13, 1979, required certain piping systems associated with Surry Power Station Unit 1 to be reanalyzed, using an appropriate piping code to account for seismic loads.

VEPCO com~lied with the order by the shutdown of Surry 1 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

The initial analysis effort to reanalyze these systems began immediately.

Major decisions were made by VEPCO concerning the course of reanalysis.

These actions had a

majQr influence on the method in which the reanalysis was completed.

These actions included:

1.

2.

3.

The use of NUPIPE computer code for all dynamic reanalysis.

The use of soil structure interaction CSSI) for the development of amplified response spectra CARS) in dynamic reanalysis.

The award of a

contract to obtain services of Quadrex <Nuclear Services Corporation) to complete a portion of the piping reanal~sis.

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SURRY POWER STATION, UNIT 1

4.

The use of field-verified input into the pipe stress reanalysis.

On April 2,

1979, a

letter was issued by the Nuclear Regulatory Commission clarifying the intent of the March 13, 1979, Show Cause Order.

This letter contained specific information concerning exactly what information was required to allow the Show Cause Order to be lifted and the plant's return to operation.

Among the requirements of the April 2, 1979, letter was a list of the material required for NRC review of reanalysis results and a

plan for verification of dynamic analysis codes.

This letter also requested response for the licensee concerning what methods of seismic analysis were employed for other systems within the show cause plants, and also, a listing of all piping systems affected by the Show Cause Order.

VEPCO's response to this letter was Serial No. 220/040279, dated May 24, 1979 Citem 22, Appendix B).

The NRC letter of April 13, 1979 (Item 3, Appendix B), informed VEPCO that use of SSI techniques for the development of amplified response spectra utilizing an elastic half-space model would be acceptable for reevaluation of piping at Surry 1 and 2.

As the Show Cause analysis continued, SSI ARS acceptability of SSI was obtained on May 25,

1979, in were employed.

an NRC letter The from D. Eisenhut the staff

<Item 5, Appendix BJ.

The completion of documentation to support review of SSI was supplied in the

report, 11Soil Structure 1-2

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I SURRY POWER STATION, UNIT 1 Interaction in Development of Amplified

Response

Spectra for Surry Power Station - Units 1 and 2."

The date of this report is June 8, 1979

<Item 26, Appendix B).

Following the acceptability of the SSI ARS by the NRC, meetings were held both in the offices of Stone & Webster in Boston, Massachusetts, and the NRC in

Bethesda, Maryland, to review the reanalysis completed and determine the acceptability of that reanalysis to allow interim plant operation.

The reanalysis completed indicated that the computer code in question had no major effect on the ability of the piping systems to withstand earthquakes.

Specific understandings were reached during these

meetings, including evaluation of the Design Basis Earthquake CDBEl, forming the basis for interim lifting of the show cause order and interim operation.

In order to develop a viable basis for interim operation of*surry Unit 1, the scope of reanalysis initially included some problems that used computer codes not addressed by the order to show cause.

These were piping problems addressed by USNRC IE Bulletin 79-04 CVelan Valves).

Also reanalyzed were SHOCK O/I piping problems.

The reanalysis of these piping systems is being completed as part of IE Bulletin 79-14 rea~ilysis.

By June 5,

1979, the reanalysis had proceeded sufficiently to allow the issuance of "The Report on the Reanalysis of Safety-Related Piping

Systems, 1-3

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SURRY POWER STATION, UNIT 1 Surry Power Station Unit 1, 11 VEPCO Serial No. 453 Citem 24, Appendix BL This report outlined the pipe stress and pipe support analysis completed to date and requested interim operation of the unit, based on the minor hardware modifications identified as of that time.

This submittal also included a

summary of the conservatisms that were being factored into the reanalysis.

This request for interim operation was refused.

As a result of the June 5, 1979, submittal, additional meetings were held with the NRC to discuss requirement for interim operation.

It was then determined that the completion of the pipe stress analysis would be necessary in order to allow interim operation.

Upon completion of the pipe stress

analysis, a

second submittal was issued on August 1,

1979, TTRevised Report on the Reanalysis of Safety-Related Piping Systems, Surry Power Station Unit l,n VEPCO Serial No. 453A Citem 31, Appendix B).

Discussions and meetings between Stone & Webster, VEPCO, and the NRC (following this submittal) led to a letter written by VEPCO on August 21, 1979 Citem 32, Appendix B).

This letter concluded that typical pipe support analysis was complete within the reactor containment and that certain systems outside the containment, as designated by the NRC, were also complete.

This letter resulted in the lifting of the Show Cause Order by the Commission, on August 22, 1979 Citem 15, Appendix B).

Surry Unit 1 was not allowed to start up at this time, based on NRC Inspection and Enforcement CI&E) concerns about the acceptability of embedded anchor bolt 1-4

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I SURRY POWER STATION, UNIT 1 inspections required per I&E Bulletin 79-02 and the work completed to date on I&E Bulletin 79-14.

The October 4,

1979, VEPCO

letter, Serial No. 817 Citem 35, Appendix Bl, to the Commission on I&E Bulletins 79-14 and 79-02, was evaluated by I&E and interim start-up was grante?

following completion of specific activities outlined in that letter.

Interim start-up of the plant occurred on October 25, 1979.

This was after VEPCO comm~tted to an expedited schedule for the reanalysis of all piping systems in accordance with I&E Bulletin 79-14.

The August 22,

1979, lifting of the Show Cause Order allowed VEPCO 60 days after startup to complete all DBE pipe support reanalysis outside the reactor containment building on the problems specifically addressed by the March 13, 1979, Order to Show Cause.

At the end of the 60 day

period, December 23,

1979, the provisions of the August 22, 1979, order were met as discussed in the VEPCO letter of December 21, 1979, Serial No. 1158 Citem 40, Appendix B).

The purpose of. this report is to document the results of the DBE reanalysis during the 60 day interval in a format similar to the June 5 and August 1, 1979, reports.

This report concludes detailed documentation of all aspects of the Design Basis Earthquake Show Cause reanalysis for Surry Power

Station, Unit 1.

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SURRY POWER STATION, UNIT 1 SECTION 2 PIPE STRESS RESULTS A

total of 63 pipe stress problems were originally analyzed by the PSTRESS/SHOCK 2 computer program that used algebraic summation and are therefore specifically addressed by the Show Cause Order.

These stress problems were analyzed by two groups: Stone & Webster Engineering Corporation CS&Wl in Boston, Massachusetts, and Nuclear Services Corporation CNSC) or Quadrex in Campbell, California, as indicated in the following table:

PIPE STRESS PROBLEMS TOTAL 42 21 63 Field-verified piping isometric drawings provide the basis for program inputs for the pipe stress reanalysis of the SHOCK 2 problems.

The reanalysis is conducted using the NUPIPE computer program.

NUPIPE calculates intra-modal seismic forces using a modified square root of the sum of the squares CSRSSl 2-1

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I SURRY POWER STATION, UNIT 1 technique which is always more conservative than the approved SRSS method, and an SRSS technique for inter-modal combination.

Additionally,. in some cases, piping is analyzed utilizing amplified response spectra CARS) that are developed using soil structure interaction techniques CSSI-ARS).

The resultant stresses and loads are used to evaluate piping, supports, nozzles, and penetrations.

In accordance with the NRC letter of May 25, 1979 to Virginia Electric and Power Company CVEPCO>, the seismic inertial stresses typical loads computed using the SSI-ARS have been increased by a

factor of 1.5 for the DBE condition.

All 63 SHOCK 2 problems have been reanalyzed and approved by S&W Engineering Assurance or NSC Quality Assurance.

Table 2-1 for the Design Basis Earthquake shows the results for these 63 stress problems.

In Table 2-1, the figures for Original Total Stress, at the point of maximum total stress in the

pipe, and Original Seismic Stress, at the same point, are extracted from Table 3-1 of the "Seismic Design Review Equipment and Piping, Surry Power Station,"

dated September 15, 1971.

The original calculations for the seismic design review report are no longer available; therefore, correlations were made to the original stresses in Table 3-1 on the basis 0 of the MSK's.

In Table 2-1, the columns for New Total Stress, at the point of maximum total stress in the pipe, and New Seismic Stress, at the same point, were taken from 2-2

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I SURRY POWER STATION, UNIT 1 the NUPIPE computer runs with the seismic inertial stress magnified by a factor of 1.5 for runs using the SSI-ARS, per the NRC letter to VEPCO of Hay 25, 1979.

Of the 63 problems in Table 2-1, 56 used the SSI-ARS and 7 used the original ARS.

The original total and original seismic stresses shown in Table 2-1 were computed using the SHOCK 2 programs for the original design conditions.

The new total and new seismic stresses were computed by the NUPIPE program using different mass models and in some cases different ARS's than the original calculations.

Hore importantly, the reanalyses were based on field-verified piping configurations in 1979, which in some cases differ from the original design conditions.

For this

reason, the new stresses and the original stresses in Table 2-1 are not comparable~ as they do not necessarily represent the same physical conditions.

Table 2-2 summarizes the nozzles and penetrations evaluated under the reanalysis progra~. All of the 84 nozzles on problems originally analyzed by the SHOCK 2 program have been found acceptable by S&W.

For those problems in which the SSI-ARS are used, the seismic inertial nozzle loads have been increased by a factor of 1.5 per the NRC letter of 25 May 1979.

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I SURRY POWER STATION, UNIT 1 The typical SHOCK 2 stress problems include 8 penetrations.

The analyses of all penetrations have been completed.

Table 2-4 lists all modifications to reduce nozzle and penetration loads.

Table 2-3 lists the hardware modifications necessary to bring the pipe stress analysis to within code allowables.

Of the 63 SHOCK 2 problems reanalyzed, hardware modifications were made to 20 problems due to pipe stress.

These modifications consisted of 63

added, modified, or deleted supports.

No physical modifications to piping were required.

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SURRY POWER STATION, UNIT 1 TABLE 2-1 PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE P.rob-Line Pioe Stress C2si>

lem System Iso.

Size Original Original New New Allow-

~

Name

~ CNPS)

Total*

Seismic* Total Seismic able

,SHOCK2 Problems 555 Low Head Safety 122 Dl 10" 29290 NA 10733 5311 30882 Injection 12 II 1555 Low Head Safety 122 Ll 12 11 25290 NA 10036 3855 30882 Injection 706A Low Head Safety 122 Hl 6"

18451 10707 15953 10024 30769 Injection 707A Low Head Safety 122 Jl 6"

22436**

19577**

19229 12556 33750< 1 >

Injection 708 Low Head Safety 122 Kl 6"

20552**

NA 17489 10941 30769

Injection 731A Low Head Safety 127 El 8"

22671**

NA 12734 5393 2997Q<l 1 5 >

Injection 731B Low Head Safety 127 E2 8"

22671 NA 13470 2033 29970<l,S>

Injection 743 Low Head Safety 127 Fl 10" 24649**

NA 14789 5496 33750 Injection 727 Low Head Safety 127 Cl 6"

28909**"*

NA 29157 26678 29970 Injection 127 C2 10" 735 High H~ad Safety 127 Gl 411 ' 6" 23011 13220 19296 15708 31104< 3 >

Injection 127 G2 8 II ' 10" 525A Containment &

123 Al 8"

11999 10866 6388 3311 33750<'1>

1525A Recirculation Spray 10" 5596 4275 33750 546/

Containment &

123 Dl 8"

560 Recirculation Spray 123 El 10" 28209 24753 10751 2291 32616<l>

546/

Containment &

123 F3 1 8" 28209 24753 21279 2658 32616 5600 Recirculation Spray 10" 1 of 7

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SURRY POWER STATION, UNIT 1 TABLE 2-1 <Cont>

PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE Prob-Line Pi2e Stress <2si) lem System Iso.

Size Original Original New New Allow-

~

Name fuh_

CNPS)

Total*

Seismic* Total Seismic able 546/

Containment &

123 F2 8"

28209 24753 21003 2499 32616 5620 Recirculation Spray 10" 548C Containment &

123 HZ 10" 15785**

11241**

5610 2685 32616(5)

Recirculation Spray 547 Containment &

123 Cl 8"

20953 5688 7451 5634 33750< 51 Recirculation Spray 10" 744/

Containment &

123 Jl 8"

26721**

NA 28136 16398 337 50 (<I) 754 Recirculation Spray 548A Containment &

123 Bl 8"

11955 11256 14927 11598 33750CS)

Recirculation Spray 10" 548B Containment &

123 Hl l0 1i 28660 26790 17028 15505 32616 Recirculation Spray '

544 Containment &

123 Gl 10" 13402 6986 9211 6133 28485 Recirculation Spray 123 G2 544A Containment &

123 R2 10" 12853 11256 6430 3556 29970 Recirculation Spray 544B Containment &

123 Rl 10" 12853 11256 6448 4541 28485 Recirculation Spray 751 Containment &

123 Nl 10" 6010 5169 7085 5206 28485 Recirculation Spray 123 N2 562 Containment &

123 Fl 10" 12610**

NA 28600 1962 32616 (.2' 5 )

Recirculation Spray 123 E2 745 Containment &

123 Kl 8"

25702 24579 25394 2148 33750Cb)

Recirculation Spray 323A Hain Steam 100 Dl 30" 13824 6343 12988 354 27000 322A Hain Steam 101 Dl 30" 13031 5548 11546 852 27000 334A Hain Steam 102 Dl 30" 18635 11082 15319 463 27000 2 of 7

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PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE Prob-Line Pi Pe Stress (psi) lem System Isa.

Size Original Original New New Allow-

~

Name li!h_

CNPS)

Total*

Seismic* Total Seismic able 346 Main Steam 103 Al 30" 19970 12563 31663 14049 33750<7>

323B Feedwater***

100 Gl 14" 15829 590 12899 8061 27000 322B Feedwater***

101 Gl 14" 17927 13521 15432 878 27000 334B Feedwater 102 Gl 14" 16025 12281 17169 10791 27000 417 Auxiliary Feedwater 118 Al 3"

8568 NA 24530 14036 27000 118 A2 607 Auxiliary Feedwater 118 Gl 411 18681 NA 18126 5347 27000 118 G2 6"

636 Pressurizer Spray 125 Al 4"

17671 9527 20304 13833 28800

& Relief 630 Pressurizer Spray 124 Al 311' 4" 20500**

NA 29421 24839 30690< 0 >

& Relief 124 A2 6"' 12" 540 Residual Heat 117 Bl 311' 411 14746**

3374**

19144 9020 25785 Removal 511' 12" 508 Residual Heat 117 Al 10"' 12 II' 16627 12375 13203 8757 25785 Removal 117 A2 14" 465 Service Water 119 Al 24" 19101 18285 6935 5826 21600 119 A2 119 A3 119 A4 488/

Component Cooling 112 c 18" 26723**

NA 16263 13680 27000 480 112 Al 507/

Component Cooling 112 Fl 311 26695**

NA 21499 19895 27000 481 112 Bl 18" 614 Component Cooling 112 AEl 12" 25448**

NA 20601 17575 27000 112 AE2 18" 112 AE2 10"' 611 512 Component Cooling 112 ANl 18" 26792**

NA 17748 15621 27000 3 of 7

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SURRY POWER STATION, UNIT 1 TABLE 2-1 (Cont>

PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE Prob-Line Pi:Qe Stress C:Qsi>

lem System

!so.

Size Original Original New New Allow-

~

Name

~ CNPS)

Total*

Seismic* Total Seismic able 603A Component Cooling 112 Sl 1811 18710 13461 5396 3554 27000 766 Component Cooling 112 AR 811 10449**

NA 19041 17263 27000 112 T 605A Component Cooling 112 AAl 311' 611' 12420 6727 20269 17990 27000*

112 AA2 1811 605B Component. Cooling 112 AAl 311, 6 II t

12420 6727 14775 11004 27000 112 AA2 1811 509A/D Component Cooling 112 Gl 811' 12 11 '

26566**

NA 20374 16992 27000 1811 ' 2411 612 Component Cooling 112 A Kl 1811 17958lOE NA 14034 9374 27000 1512 Component Cooling 112 J 1811 26792**

NA 21455 19998 27000 2529/

Component Cooling 112 AH 3"' 6 II t 26701**

NA 18405 16809 27000 2527 811' 1011 '

1411 ' 1811 2526 Component Cooling 112 AJ 2'2", 6"' NA NA 24840 16269 27000 811' 10" 517 Component Cooling 112 Ml 4"' 6"'

17958**

NA 14686 13239 27000 112 M2 811' 10 11 '

112 M3 14"' 1811 603B Component Cooling 112 Sl 18" 18710 13461 5794 2624 27000 526C Component Cooling 112 Ll 6 II t 811 NA NA 22573 22258 27000 112 L2 112 L3 527A/C Component Cooling 112 Tl 411 ' 6"'

10449**

NA 22803 21266 27000 112 Tl 8"' 1011 '

1411 509B Component Cooling 112 G2 8"' 12"'

26566**

NA 22705 19319 27000 18"' 24" 4 of 7

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SURRY POWER STATION, UNIT 1 TABLE 2-1 <Cont>

PIPE STRESS REEVALUATION SUMl1ARY DESIGN BASIS EARTHQUAKE Prob-Line Pipe Stress <2si>

lem System Isa.

Size Original Original New New

~

Name tl_9_:_

CNPS)

Total*

Seismic*

Total Seismic 509C Component Cooling 112 G3 8" ' 12"'

26566'lOE NA 18862 16007 18"' 24" CVl Containment Vacuum 137 Al 8"

25750**

NA 16039 1824 746 3" HP Steam 131 Al 3"

26 766lOE NA 18674 11200 131 B2 4"

131 C3 CFl Fire Protection 144 Al 2"' 6",

22255**

NA 9911 8353 12 II CF2 Fire Protection 144 Bl 1 l/2",

10966**

37 33lOE 5323 1190 2 II' 16 11 1040 Diesel Muffler Exhaust 143 Al 24" 11857**

NA 7340 6756 LEGEND:

Table 2-1 of Seismic Design Review Equipment and Piping Surry Power Station, September 1971, or

- Subsequent reanalysis.

Allow-able 27000 27000 27000' 27000 27000 22500

- - Max stress of feedwater inside reactor containment only.

The flow diagram in the June 5, 1979 submittal is correct.

The flow diagram in the August 1, 1979 submittal inadver-tently included a small portion of feedwater.

Piping outside the reactor containment is in error.

Feedwater outside the reactor containment is part of the I&E 79-14 effort.

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NA = Not Available SURRY POWER STATION, UNIT 1 TABLE 2-1 CCont)

PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE Allowable Stress = 1.8 S New Total Stress = S

+ s.

+ 1.5 s

+ s Cfor SSI/ARS)

New Seismic = 1.5 S C for SS I/ ARS )

New Total Stress = S

+ s

New Seismic = S (original ARS)

NOTE:

The original total*

and original seismic* stresses shown in Table 2-~ w~re computed using SHOCK2 for the original design conditions.

The new total and new seismic stresses were computed by the NUPIPE program using different mass models and, in some cases, different ARS's than the original calculations.

More importantly, the reanalyses were based on field-verified, piping configurations in 1979, which, in some cases, differ significantly from the original design conditions.

For this reason, the new stresses and the original stresses in Table 2-1 are not comparable, as they do not necessarily represent the same physical conditions.

DESCRIPTIVE NOTES CTo explain differences between the August 1, 1979 table and table submitted in this report):

1.

The high stress point occurs on a portion of the piping with a lower temperature therefore the higher allowable.

2.

Pipe supports were added or modified to reduce loads on other existing supports.

This stress analysis performed since the August 1, 1979 submittal.

3.

The high stress point occurs on a portion of the piping with a higher temperature therefore

4.

the lower allowable.

1 In the original stress analysis therefore only one analysis made.

separate pipe stress runs be made.

to pipe support analysis.

both spray headers were considered as being similar As-built differences in pipe supports caused two This resulted in different hardware modifications due

5.

System operating temperature revised therefore allowable stress changed accordingly.

6.

Problem rerun with revised building displacements.

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SURRY POWER STATION, UNIT 1 TABLE 2-1 CCont)

PIPE STRESS REEVALUATION

SUMMARY

DESIGN BASIS EARTHQUAKE

7.

Pipe stress problem rerun with enveloped ARS for 3-buildings.

New run of record made in preparation for OBE support analysis.

8.

Since the high stress point occurs at the point where two piping classes join, the lower allowable should be applied.

9.

Problem rerun with revised building displacements and modified NUPIPE.model.

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I SURRY POWER STATION, UNIT 1 I

TABLE 2-2 I

NOZZLE AND PENETRATION

SUMMARY

SHOCK 2 PROBLEMS DESIGN BASIS EARTHQUAKE I

No. Accep-Modifi-Vendor System Total No.

table cations or Confirmation I

and of Nozzles/

Evaluation No. Under Additions Being Prob. No.

Penetrations CComolete)

Evaluation Reouired Obtained I

Low Head Safety Injection I

555 1

1 0

0 Confirmed 1555 1

1 0

0 Confirmed I

706A o*

N/A N/A N/A N/A I

707A 0

N/A N/A N/A N/A 708 0

N/A N/A N/A N/A I

731A 0

N/A N/A N/A N/A 731B 0

N/A N/A N/A N/A I

743 0

N/A N/A N/A N/A I

727 2

2 0

0 Confirmed High Head I

Safety Injection 735 3

3 0

0 Confirmed I

Containment Recirculation I

So ray 525A/l525A 0

N/A N/A N/A N/A I

546/560 1

1 0

0 N/A 546/5600 0

N/A N/A N/A N/A I

546/5620 0

N/A N/A N/A N/A I

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TABLE 2-2 (Cont)

I NOZZLE AND PENETRATION

SUMMARY

SHOCK 2 PROBLEMS DESIGN BASIS EARTHQUAKE I

No. Accep-Modifi-Vendor System Total No.

table cations or Confirmation I

and of Nozzles/

Evaluation No. Under Additions Being Prob. No.

Penetrations

<Comolete)

Evaluation Reouired Obtained I

548C 1

1 0

0 NIA 547 0

NIA NIA NIA NIA I

7441754 1

1 0

0 Confirmed 548A 0

NIA NIA NIA NIA I

548B 1

1 0

0 NIA I

544 212 212 010 010 NIA 544A 2

2 0

0 Confirmed I

544B 2

2 0

0 Confirmed 751 2

2 0

0 NIA I

562 1

1 0

0 NIA I

745 1

1 0

0 Confirmed Hain Steam I

323A 111 111 010 010 NIA 322A 111 111 010 010 NIA I

334A 111 111 010 010 NIA I

346 010 NIA NIA NIA NIA Feedwater I

323B 111 111 010 010 NIA 322B 111 111 010 010 NIA I

334B 111 111 010 010 NIA I

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I SURRY POWER STATION, UNIT 1 I

TABLE 2-2 <Cont)

I NOZZLE AND PENETRATION

SUMMARY

SHOCK 2 PROBLEMS DESIGN BASIS EARTHQUAKE I

No. Accep-Modifi-Vendor System Total No.

table cations or Confirmation I

and of Nozzles/ Evaluation No. Under Additions Being Prob. No.

Penetrations

<Comolete)

Evaluation Reouired Obtained I

605B 3

3 0

0 Confirmed 509A/D 3

3 0

0 N/A I

612 2

2 0

0 Confirmed 1512 0

N/A N/A N/A N/A I

2527/2529 2

2 0

0 Confirmed I

2526 0

N/A N/A N/A tUA 527A/C 2

2 0

0 Confirmed I

517 4

4 0

0 Confirmed 603B 1

1 0

0 Confirmed I

526C 0

N/A N/A N/A N/A I

509B 0

N/A N/A N/A N/A 509C 0

N/A N/A N/A N/A I

Containment Vacuum I

CVl 0

N/A N/A N/A tUA 3" HP Steam I

746 1

1 0

0 Confirmed Fire Protection I

CF-1 0

N/A N/A N/A N/A I

CF-2 0

N/A N/A N/A N/A I

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Diesel Muffler Exhaust 1040 SURRY POWER STATION, UNIT 1 TABLE 2-2 CCont)

NOZZLE AND PENETRATION

SUMMARY

SHOCK 2 PROBLEMS DESIGN BASIS EARTHQUAKE No. Accep-Total No.

table of Nozzles/

Evaluation No. Under Penetrations CComolete)

Evaluation 3

3 0

N/A = not applicable 5 of 5 Modifi-Vendor cations or Confirmation Additions Being Reouired Obtained 0

N/A

Problem MKS No.

No.

System 334B 508 102Gl,G2 FW 540 548A 562 727 735 743 744/7 54 745 746 ll 7Al ll 7Bl 123Bl 123E2 127Cl 127Gl 127Fl 123Jl 123Kl 131Al B2 C3 RHR RHR C&RS C&RS LHSI HHSI LHSI C&RS C&RS HP Steam SURRY POWER STATION, UNIT 1 TABLE 2-3 PIPE STRESS HARDWARE MODIFICATION

SUMMARY

Overstressed Condition Thermal overstress DBET overstressed RHR pump Discharge elbows and overloaded nozzles.

1. Thermal overstress due to support which was not included in original analysis.

2. Overstress in 2" line which was not included in original analysis.

DBEI overstress condition DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress

DBEI overstress 1 of 2 Attributable To:

As-Built Seismic Reanalysis As-Built As-Built As-Built Seismic Reanalysis As-Built As-Built As-Built As-Built As-Built Resolution Delete U-Bolt**

Six supports added to alleviate overstress condition.

1. Delete NS & RH's.

2. Add Anchor to 2" line.

Addition of a horizontal snubber.

Addition of EW.

Replace RH with SH.

Replace SH with VC.

Addition of an LSS.

Addition of two guides.

Shim existing constraint to VC/LC.

Modification and re-placement of constraints to reflect original analysis.

Modification and addition of constraints to reflect original analysis.

I!

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

Problem No.

488/480 507/481 509A/D 517 526C 527A/C 605A 766 2527/2529 NOTES:

MKS No.

System 122Al,Cl CCW 112Bl I Fl ccw 112G ccw 112M ccw 1121 ccw 112T ccw 112AA ccw 112AR ccw 112 ccw SURRY POWER STATION, UNIT 1 TABLE 2-3 (Cont)

PIPE STRESS HARDWARE MODIFICATION

SUMMARY

Overstressed Condition DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBE! overstress DBEI overstress DBEI overstress and thermal overstress DBEI overstress Attributable To:

As-built As-built As-built As-built Seismic Reanalysis Seismic Reanalysis As-built As-built As-built As-built Resolution Add two guides to Problem 480 and two lateral restraints to Problem 488.

Add two guides to Problem 481.

Added one vertical restraint.

Seven restraint changes are required.

Added a lateral restraint and modify an SH to a rigid vertical constraint.

Delete anchor A36 and shim supports.

Add four lateral restraints.

Add horizontal guides and delete an axial restraint.

Delete anchor and shim supports.

The use of ARS curves causes higher acceleration levels than the procedure for below-grade structures formerly used as described in the Seismic Design Review revised September 15, 1971.

- Due to Branch-Line Analysis FW = Feedwater RHR = Residual Heat Removal C&RS = Containment & Recirculating Spray System LHSI = Low Head Safety Injection HHSI = High Head Safety Injection HP Steam = High Pressure Steam CCW = Component Cooling Water NS = North-South Constraint RH's = Rod Hangers EW = East-West Constraint 2 of 2 RH = Rod Hanger SH = Spring Hanger VC = Vertical Constraint LC = Lateral Constraint

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I Problem

No.

746 746 746 746 746 746 322B 323B 334B SURRY POWER STATION, UNIT 1 TABLE 2-4 HARDWARE MODIFICATION

SUMMARY

DUE TO NOZZLE AND PENETRATION OVERLOADING Attributable Overstress No.

To:

Resolution l-FW-P-2 inlet nozzle As-Built/

Add vertical shock thermal suppressor l-FW-P-2 inlet nozzle As-Built/

Add vertical shock thermal suppressor 1-FW-P-2 inlet nozzle As-Built/

Add spring hanger thermal l-FW-P-2 inlet nozzle As-Built/

Add north/south shock thermal suppressor 1-FW-P-2 inlet nozzle As-Built/

Replace LC by spring thermal hanger l-FW-P-2 inlet nozzle As-Built/

Add spring hanger thermal Feedwater penetration Seismic Add guide reanalysis Feedwater penetration Seismic Add guide reanalysis Feedwater penetration Seismic Add guide reanalysis 1 of 1

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SURRY POWER STATION, UNIT 1 SECTION 3 PIPE SUPPORT RESULTS Tables 3-lA and 3-lB summarize the pipe supports evaluated in the reanalysis program.

There are 944 supports C487 inside containment, 457 outside containment) on lines originally analyzed by SHOCK 2.

All 944 pipe supports have been reanalyzed, and 137 pipe support hardware modifications have been identified.

The modifications identified, due to pipe support analysis, are listed in Table 3-2.

In cases where SSI-ARS was

used, the DBE seismic inertial reactions on supports are multiplied by 1.5.

Anchor movements are not considered in the calculation of support stresses for the DBE conditions.

3-1

I SURRY POWER STATION, UNIT 1

I TABLE 3-lA PIPE SUPPORT STATUS SUHHARY INSIDE CONTAINMENT -

SHOCK 2 I

No. Accep-Modifica-System table tions or

I and Total No. of CEvaluation No. Under Additions Prob. No.

Suoports Comolete)

Evaluation Reouired Comment Low Head

,I Safety Injection I

555 14 14 4

706A 10 10 I

707A 9

9 708 22 22 3

I 1555 9

9 I

Containment and Recircu-lation SoraY I

525A/l525A 35 35 5

544 12 12 2

I 544A 6

6 I:

544B 6

6 1

546/560 18 18 6

'I 546/5600 11 11 2

546/5620 11 11 1

I 547 13 13 I

548A 2

2 548B 22 22 4

I 548C 25 25 2

562 19 19 5

-~-~ I 1 of 3 a

System and Prob. No.

Main Steam 322A 323A 334A Feedwater 322B 323B 334B Auxiliary Feedwater 417 Pressurizer Spray and Relief 630 636 Residual Heat Removal 508 540 Service Water 465 SURRY POWER STATION, UNIT 1 TABLE 3-lA CCont)

PIPE SUPPORT STATUS SUlfrfARY INSIDE CONTAINMENT -

SHOCK 2 No. Accep-table Total No. of

<Evaluation No. Under Suooorts Complete)

Evaluation 5

5 17 17 3

3 8

8 14 14 8

8 26 26 27 27 33 33 50 50 10 10 8

8 2 of 3 Modifica-tions or Additions Reouired l

1 3

1 Comment

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System and

,I Prob. No.

Component I

Cooling 603A I

603B I

605A 605B I

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SURRY POWER STATION, UNIT 1 TABLE 3-lA CCont)

PIPE SUPPORT STATUS

SUMMARY

INSIDE CONTAINMENT -

SHOCK 2 No. Accep-table Total No. of (Evaluation No. Under SUPPOrts Complete)

Evaluation 7

7 5

5 17 17 10 10 3 of 3 Modifica-tions or Additions Reouired Comment 3

2 3

2

I SURRY POWER STATION, UNIT 1 r I TABLE 3-lB I

PIPE SUPPORT STATUS

SUMMARY

OUTSIDE CONTAINMENT -

SHOCK 2 I

No. Accep-Modifica-System table tions *or and Total No. of (Evaluation No: Under Additions I

Prob. No.

Suooorts Comolete)

Evaluation Required Comment Low Head I

Safety Iniection I

727 21 21.

731A 4

4 3

I 731B 4

4 2

743 5

5

..-.... I High Head Safety I

Injection 735 43 43 4

.1, I

Containment and Recircu-lation Sorav I

744/7 54 10 10 745 8

8 1

,1 751 6

6 I

Main Steam 346 54 54

--l 1

Auxiliary Feedwater I.

607 15 15 1

1*

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System and I

Prob. No.

Component

.. I Cooling 488/480 I

5071481 I

509AID 509B I

509C 512 1*

517 526C I

527A/C

~-

612 I

614 I

766 1512 I

2526 I

252712529 Containment I

Vacuum C\\Jl

,--I 3 11 HP Steam 746 I

I SURRY POWER STATION, UNIT 1 TABLE 3-lB (Cont)

PIPE SUPPORT STATUS

SUMMARY

OUTSIDE CONTAINMENT -

SHOCK 2 No. Accep-Modifica-table tions or Total No. of (Evaluation No. Under Additions Suooorts Comolete)

Evaluation Reouired 26 26 5

20 20 4

27 27 9

6 6

3 2

2 5

5 3

34 34 7

11 11 3

13 13 3

15 15 l

14 14 8

17 17 6

6 6

3 11 11 5

14 14 4

3 3

1 19 19 2 of 3 Comment

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System and Prob. No.

Fire Protec-tion CFl CF2 Diesel Muffler 1040 NOTES:

SURRY POWER STATION, UNIT 1 TABLE 3-lB <Cont)

PIPE SUPPORT STATUS

SUMMARY

OUTSIDE CONTAINMENT -

SHOCK 2 No. Accep-table Total No. of

<Evaluation No. Under Modifica-tions or Additions Supports Complete)

Evaluation Reouired 10 10 5

4 4

2 18 18 3

Comment The number in the "Modificationsrr or 11Additions 11 column are already included in the status shown in the rrAcceptable CComplete) 11 column.

The number in the 11Total Supports 11 column equals the number in the 11Acceptable 11 plus the number in the "Under Evaluation11 column.

The number in the 11modifications 11 or 11addi tions 11 columns does not include 11modifications" or 11additions 11 due to stress, nozzle/penetration, branch line analysis.

3 of 3

Problem No.

334B 465 508 508 508 525A 525A 544 544 544B 548B 548B 548B 548B 548C 548C SURRY POWER STATION, UNIT 1 TABLE 3-2 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Description of Modified Since Support Modification or August 21, 1979 Attributable No.

Overstressed Condition PT 90 H-21 H-42A PT 26 H-20 Hl4 H70 H34A H37A H46 H87 H72A H72B H84 Hl8A Hl8B Hl7A Hl7B Hl7C H75 Snubber modification No Support member overstressed No Snubbers over allowable No Snubbers over allowable No Weld over allowable No Prevents growth in one No direction Support overloaded No Overstressed with new loads No Overstressed with new loads No Weld over stress allowable No No lateral restraint No capability 6-way restraint not No properly functioning No lateral movement due to No thermal and seismic U-bolts overstressed No Lugs overstressed on gang No hanger - anchor U-bolt subjected to lateral No loads over allowable loads Submittal To:

1 of 10 Seismic Reanalysis As-built Seismic Reanalysis Seismic Reanalysis As-built As-built As-built As-built As-built As-built As-built As-built As-built As-built As-built As-built Resolution Add horizontal shock suppressor.

Removed Support H-21.

Add horizontal snubber.

Add horizontal and vertical snubbers.

Modify support.

Redesigned and modified to VC-LC.

Support modified.

Redesigned and modified support to receive lateral load.

Redesigned (modified to 3-way restraint).

Restore to original configuration.

Redesigned and modified support by adding bracing member.

Redesigned and modified by removing attachments to relieve pipe overstress conditions.

Replace U-bolt with framed member.

U II.. -..,....._ __.. - -.. -*--*-----

SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDTJARE MODIFICATION SUMHARY Problem No.

555 555 555 555 546/560 546/560 546/560 546/560 546/560 546/560 562 562 562 562 Description of Modified Since Support Modification or August 21, 1979 Attributable No.

Overstressed Condition HlO H28 H29 H30 H39A H39B PT-185 PT-208 PT-130 PT-216 PT-310 H26 H29A H29B PT-265 PT-340 Integral attachment overstressed No Horizontal and vertical No structural member restraining pipe movement Vertical member restraining No pipe motion Vertical member restraining No pipe motion Integral attachment over-No stressed for support H39A Added due to H39A No Added due to H39A No Added due to H39A No Added due to H39A No Added due to H39A No Modified due to H39B. Inte-No gral attachment overstressed for H39B.

Modified due to H39B.

Inte-No gral attachment overstressed for H39B.

Added due to H39B. Integral No attachment overstressed for H39B.

Modified due to H39B. Inte-No gral attachment overstressed for H39B.

Submittal To:

2 of 10 Seismic Reanalysis Thermal Movement Thermal movement Thermal movement As-built As-built As-built As-built As-built As-built As-built As-built As-built As-built Resolution Add lateral shock suppressor.

Restore to original intent.

Replace anchor by a 3-way restraint.

Add vertical shock suppressor to reduce loads.

Add lateral constraint.

Add lateral constraint and vertical constraint.

Add lateral constraint.

Modify support by adding U-bolt.

Modify 2-vay support to 3-way support.

Add lateral constraint. Reduce loads at anchor point.

Modify vertical constraint.

Problem Support No.

No.

562 PT-183 546/5600 Hl5B 546/5600 PT-155 546/5620 PT-230 636 H36 708 PT-1 708 Hl27 708 PT-380 1525A PT-5000 1525A PT-8000 1525A I PT-5802 603A 3,

603A 7

603A 5

SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Description of Modified Since Modification or August 21' 1979 Attributable Overstressed Condition Submittal To:

Added due to H39B. To redu~e No As-built load on hanger H39B.

U-bolt modified to reduce

No Seismic loads on Hl7B Reanalysis Added to reduce anchor loads No Seismic Reanalysis Added to reduce anchor loads No Seismic Reanalysis Plate overstressed No As-built Lateral load on U-bolt No As-built overstressed Member overstressed No As-built Lateral restraint over-

'No As-built stressed Delete due to H-2 No Seismic Reanalysis U-bolt and frame over-No Seismic stressed Reanalysis Hanger overloaded No Seismic Reanalysis Pipe straps overstressed No As-built Pipe straps overstressed No As-built Vertical restrainj: only re-No As-built quired, but support had zero lateral clearance.

3 of 10 Resolution Add 2-way support.

Redesigned and modified ganghanger from 1-way CLC).

Add LC-VC to-reduce loads at anchor.

Add LC-VC to reduce loads.

Modify anchor by adding gusset.

Add lateral restraint.

Modify support to vertical and lateral constraint.

Delete axial support and 1-way LC to reduce anchor load.

Modify frame.

Modify support..

Add gussets to all and increase weld size.

Modify support to provide lateral clearance.

,. n Problem No.

603B 603B 605B 605B 605A 605A 605A 607 731A 731A 731B 745 731A 731B 735 SURRY POWER STATION, UNIT 1 TABLE 3-2 C Cont)

PIPE SUPPORT HARDWARE MODIFICATION SUHMARY Description of Modified Since Support Modification or No.

Overstressed Condition August 21, 1979 Attributable 13 10 4

Uplift restraint is re-No quired, but support had negative vertical restraint only.

Vertical support only re-No quired, but support is a vertical restraint and lateral restraint.

Support members overstressed No H-2 Lateral clearance No insufficient PT-13 Need vertical restraint No 2020 Delete lateral restraint No 2005 Delete lateral restraint No PT 335 U-Bolt overstressed No SI-C-90 Support member overstressed No PT 46 Integral attachment over-No stressed SI-C-91 Support member overstressed No PT 45 Support overstressed No PT 38 Support overstressed No PT 36 Support overstressed No PT 20 Support overstressed No Submittal To:

4 of 10 As-built As-built As-built Thermal movement As-built As-Built As-Built As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis As-Built Seismic Reanalysis Seismic Reanalysis As-Built Resolution Modify support to provide uplift restraint.

Remove top and side members of support.

Replace two W4x13 members with TS4x4xl/2.

Modify restraint.

Modify vertical support.

Modify support.

Delete U-Bolt.

Add structural brace.

Add N-S restraint.

Gang Hanger Problem #731B Point #44.

Add structural brace.

Modify support.

ll 9 - -

Problem No.

735 735 735 480/488 480/488 480/488 507 507 507 507 509AD 509AD 509AD 509AD 509AD SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Description of Modified Since Support Modification or August 21, 1979 Attributable No.

Overstressed Condition Submittal To:

PT 35 Support overstressed No PT 50 Support overstressed No PT 60 Ganged support overstressed Note 2. Yes 1

Integral attachment Note 1. Yes 2,10,16 Weld overstressed Note 1. Yes Gang 3,11,17 Integral attachment Note 1. Yes Gang overstressed l

Integral attachment Note 1. Yes overstressed 4,9,15 Support overstressed Note 1. Yes Gang 5,10,16 U-bolt overstressed Note 1. Yes Gang 6,11,17 Support members and Note 1. Yes Gang weld overstressed 5

U-bolt and weld over-Note 1. Yes stressed 7

U-bolt and support Note 1. Yes overstressed 8,9,13 Support overstressed Note 1. Yes (ganged with HS, Pro. #517, HS, P:rn. tt1512>

15 U-bolt and support Note 1. Yes overstressed 4,20, Uplift restraint required Note l. Yes 24,42 5 of 10 As-Built As-Built As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis As-Built Seismic Reanalysis Seismic Reanalysis As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Resolution Modify support.

Modify support.

Modify support by adding welds.

Modify support by increasing trunnion size.

Modify support by remoding trunnion and adding frame.

Modify support by replacing u-bolt and adding new members.

Modify support by adding stiffners.

Modify support by replacing U-bolt and adding new members.

Modify support by replacing U-bolt and adding frame.

Modify support by redesigning.

Modify support by replacing vs with vc.

Modify support by adding strut.

Modify support by vs with vc.

SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Description of Modified Since Problem Support Modification or August 21, 1979 Attributable No.

No.

Overstressed Condition Submittal To:

Resolution 509AD 22 Support overstressed.

Note 1. Yes Seismic Modify support by removing trunnion Reanalysis and providing frame.

509AD 47 Support overstressed Note 1. Yes As-Built Hodify support by adding new sliding plate.

509AD 44 Uplift restraint required Note 1. Yes Thermal Modify VC to.vs.

Movement 509AD 45,46 Support overstressed Note 1. Yes Seismic Modify support to provide uplift Reanalysis restraint.

517 1

Integral welded attachments Note 1. Yes Seismic Add pad, add braces.

overstressed Reanalysis 517 16 Integral attachments Note 1. Yes Seismic Modify support by relocating overstressed Reanalysis trunnion.

517 21 Support overstressed Note 1. Yes Seismic Modify support by adding Reanalysis stiffeners.

517 22 Support member over-Note 1. Yes Seismic Modify support.

stressed.

Reanalysis 517 25 Support overstressed Note 1. Yes Seismic Replace RM with strut.

Reanalysis 517 27 Support overstressed Note 1. Yes Seismic Replace rod hanger by sway strut.

Reanalysis 517 28,35 Weld overstressed Note 1. Yes As-Built Modify support by adding brace.

526C 4

Support overstressed Note 1. Yes As-Built Modify support by adding (ganged with HB Pro. tt527AC) stiffeners.

526C 6

Integral attachment Note 1. Yes Seismic Replace support by clamp anchor overstressed Reanalysis assembly.

526C 11 Integral attachment Note 1. Yes Seismic Modify support by relocating overstressed Reanalysis trunnion.

527AC 1

Support member over-Note 1. Yes Seismic Modify support by adding stressed Reanalysis base plates.

6 of 10 H

SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Problem No.

527AC 527AC 1512 1512 1512 2527 2527 2527 2529 1040 CVI CF-1 Description of Support Modification or No.

Overstressed Condition 3

4 3

6 7

3 5

7 13 PT 57 PT 57 PT 57 PT 38 1

2 5

U-bolt overstressed Support overstressed Support overstressed Support overstressed Support overstressed U-bolt overstressed Support overstressed U-bolt overstressed Clevis overstressed Additional support Additional support Additional support Support overstressed Bolts and structure overstressed Support overstressed Uplift problem Modified Since August 21, 1979 Attributable Submittal To:

Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note ;... Yes Note 1. Yes Note. 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes 7 of 10 As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis As-Built As-Built As-Built As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Resolution Modify support by replacing u-bolt and adding frame; Modify support.

Add sway strut for side load.

Modify support by replacing U-bolt.

Modify support by adding plates.

Modify support by replacing U-bolt and adding welded frame.

Replaced with new support.

Modify support by replacing U-bolt.

Replace clevis with rod and clamp.

Add 1 vertical snubber Diesel 1.

Add 1 vertical snubber Diesel 2.

Add 1 vertical snubber Diesel 3.

Modify support.

Add brace CS&W) increase weld size.

Sway struts added.

Remove angle, add sway strut.

ti I! - -

Problem No.

CF-2 488 509B 512 612 614 SURRY POWER STATION, UNIT 1 TABLE 3-2 CCont)

PIPE SUPPORT HARDWARE MODIFICATION SUHMARY Description of Modified Since Support Modification or August 21, 1979 Attributable 13 14 2

4 21 22 6

19 28 3

6 8

4 1

2 No.

Overstressed Condition Uplift problem Uplift problem U-bolt overstressed Weld overstressed Improper support Submittal To:

Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Weld and bolts overstressed Note 1. Yes Seismic Reanalysis Weld overstressed Integral welded attachment overstressed U-bolt overstressed Structure, weld and U-bolt overstressed Structure, weld and U-bolt overstressed Integral welded attachment overstressed Structure and weld over-stressed Structure overstressed ganged with H27 Pro. #509B Structure and U-bolt Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes 8 of 10 Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Resolution Replace rod hanger with sway strut.

Replace rod hanger with sway strut.

Replace with frame.

Added weld and gusset plater.

Add baseplate and shims.

Increase weld, add brace CS&W>.

Increase weld.

Add pad, brace CS&W>.

Remove support, add frame w/brace.

Modify support, r~move support, add frame.

Add pad; add braces.

Shorten stanchion.

Replace U-bolt w/frame, add brace.

Problem No.

766 SURRY POWER STATION, UNIT 1 TABLE 3-2 (Cont)

PIPE SUPPORT HARDWARE MODIFICATION SUIB1ARY Description of Modified Since Support Modification or August 21, 1979 Attributable 5

7 8

9 10 13 5

7 8

9 14 15 No.

Overstressed Condition Submittal To:

overstressed Support structure over-stressed (ganged with H31, Pro. tt509B, H7 Pro. #512)

Structure and U-bolt overstressed Improper support Structure overstress Integral welded attachment overstressed Uplift restraint required Support structure and weld overstressed (ganged with H39, Pro. #517)

Note 1. Yes Note l._ Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Note 1. Yes Support, structure over-Note 1. Yes stress (ganged with H32, Pro. lt517)

Support uplift over-Note 1. Yes stress problem (ganged with H33, Pro. #517)

Support weld overstressed Note 1. Yes and uplift (ganged with H34, Pro. 11517)

U-bolt, welds and structure Note 1. Yes overstressed Structure and weld over-Note 1. Yes stress 9 of 10 Reanalysis Seismic Reanalysis Seismic Reanalysis As-Built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Support Reanalysis Support Reanalysis Support Reanalysis Support Reanalysis Support Reanalysis Support Reanalysis Resolution Revise IWA; add lateral brace and closure plate to column.

Replace U-bolt w/beams, add brace.

Restrain pipe in correct direction.

Add gussets.

Replace exist. support w/lWA and frame to floor.

Replace vs by vc.

Modify support.

Reanalyzed and restrain uplift.

Remove U-bolt, add frame and brace.

Add braces.

Problem No.

2526 NOTES:

SURRY POWER STATION, UNIT l TABLE 3-2 (Cont)

PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

Description of Modified Since Support Modification or August 21, 1979 Attributable 1

6 9

18 20 No.

Overstressed Condition Submittal To:

Support overstress (ganged with H4, Pro. #512, H2, Pro. tt2529)

Note 1. Yes Integral welded attachment Note 1. Yes overstressed Uplift problem Note l. Yes Vertical, lateral, axial Note 1. Yes restraint required by pipe stress due to H20 overstress Integral welded attachment Note 1. Yes overstressed Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis

1.

Modification outside containment.

2.

Modified prior to interim operation as required per August 22, 1979 order.

10 of 10 Resolution Modify support.

Add pad.

Replace rod hanger with sway strut.

Replace rod hanger w/frame, add lugs to modified support.

Rerun NUPIPE revise Hl8, and replace IWA w/(2) IWAs.

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I SURRY POWER STATION, UNIT 1 APPENDIX A CROSS REFERENCE OF MKS, FM, FP, PROBLEM NO., SYSTEM

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SURRY POWER STATION, UNIT 1 APPENDIX A CROSS REFERENCE OF MKS, FM, FP, PROBLEM NO., SYSTEM MKS FM FP Problem System lOODl 1148-FM-14 11448-FP-l 323A Main Steam 101Dl 11448-FP-1 11448-FP-1 322A Main Steam 102Dl 11448-FH-14 11448-FP-1 334A Main Steam 103Al 11448-FM-14 11448-PP-1 346 Main Steam 103A2 11448-FM-14 11448-PP-l 346 Hain Steam 131Al 11448-FM-14 11448-FP-5 746 3" High Press Steam 131B2 11448-FH-14 11448-FP-5 746 3" High Press Steam 131C3 11448-FM-14 11448-FP-5 746 311 High Press Steam lOOGl 11448-FM-18 11448-FP-2 323B Feedwater 101Gl 11448-FM-18 11448-FP-2 322B Feedwater 102Gl 11448-FM-18 11448-FP-2 334B Feedwater ll8Al 11448-FM-18 11448-FP-2 417 Aux Feedwater 118/\\2 11448-FM-18 11448-FP-2 417 Aux Feedwater ll8Gl 11448-FH-18 11448-FP-2 607 Aux Feedwater l18G2 11448-FM-18 11448-FP-2 607 Aux Feedwater 119Al 11448-FH-21 11448-FP-4 465 Service Water ll9A2 11448-FH-21 11448-FP-4 465 Service Uater 119A3 11448-FH-2 l 11448-FP-4 465 Service Water ll 9A4 11448-FH-21 11448-FP-4 465 Service Water 112/\\l 11448-FM-22 11448-FP-16 480 Component Cooling 112Bl 11448-FH-22 11448-FP-16 481 Component Cooling 112Cl 11448-FH-22 11448-FP-16 448 Component Cooling 112Fl 11448-FH-22 11448-FP-16 507 Component Cooling 112Gl 11448-FH-22 11448-FP-16 509AD Component Cooling 112G2 11448-FH-22 11448-FP-16 509B Component Cooling 112G3 11448-FH-22 11448-FP-16 509C Component Cooling 112G4 11448-FH-22 11448-FP-16 509AD Component Cooling 112Jl 11448-FH-22 11448-FP-16 1512 Component Cooling 112Ll 11448-FM-22 11448-FP-16 526C Component Cooling 11212 11448-F'M-22 11448-FP-16 526C Component Cooling 11213 11448-FH-22 114l~8-FP-16 526C Component Cooling 112Hl 11448-FH-22 11448-FP-16 517 Component Cooling 112H2 11448-FH-22 11448-FP-16 517 Component Cooling 112H3 11448-FH-22 11448-FP-16 517 Comoonent Cooling 112Sl 11448-FH-22 11448-FP-16 603/\\&B Component Cooling 112Tl 11448-FH-22 11448-FP-16 527 A/C Component Cooling 112T2 11448-FM-22 11448-FP-16 527 J\\/C Component Cooling 112T3 11448-FH-22 11448-FP-16 527A/C Component Cooling 112AA1 11448-FH-22 11448-FP-16 605A&B Component Cooling 112AA2 11448-FH-22 11448-FP-16 605A&B Component Cooling A-1

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SURRY POWER STATION, UNIT 1 APPENDIX A (Cont)

CROSS REFERENCE OF MKS, FM, FP, PROBLEM NO., SYSTEM MKS FM FP Problem System 112AE1 11448-FM-22 11448-FP-16 614 Component Cooling 112AE2 11448-FH-22 11448-FP-16 614 Component Cooling 112/\\Hl 11448-FM-22 11448-FP-16 2529 Component Cooling 112AH2 11448-FH-22 11448-FP-16 2529 Component Cooling 112/\\Jl 11448-FH-22 11448-FP-16 2526 Component Cooling 112AJ2 11448-FH-22 11448-FP-16 2526 Component Cooling 112/\\Kl 11448-FH-22 11448-FP-16 617 Component Cooling 112AL1 11448-FH-22 11448-FP-16 2527 Component Cooling 112AN1 11448-FH-22 11448-FP-16 512 Component Cooling 112AB1 11448-FM-22 11448-FP-16 766 Component Cooling 112AR2 11448-FH-22 11448-FP-16 766 Component Cooling 122Dl 11448-FH-106 11448-FP-ll 555 Low Head Safety INJ 122Hl 11448-FM-106 11448-FP-3, 10 706A Low Head Safety INJ 122Jl 11448-FM-106 11448-FP-3, 10 707/\\

Low Head Safety INJ 122Kl 11448-FH-106 11448-FP-3, 10 708 Low Head Safety INJ 122Ll 11448-FH-106 1448-FP-ll 1555 Low Head Safety INJ 127Cl 11448-FH-106 11448-FP-60 727 Low Head Safety INJ 127C2 11448-FH-106 11448-FP-60 727 Low Head Safety INJ 127£1 11448-FH-106 11448-FP-5, 10 731A Low Head Safety INJ 127E2 11448-FH-106 11448-FP-5, 10 731B Low Head Safety INJ 127Fl 11448-FH-106 11448-FP-5, 10 743 Low Head Safety INJ 127Gl 11448-FH-105, 106 11448-FP-10 135 High Head Safety INJ 127G2 11448-FH-105, 106 11448-FP-10 735 High Head Safety INJ 123/\\1 11448-FH-lOlA 11448-FP-13 525A Cont&Recirc Spray 123A2 11448-FM-lOlA 11448-FP-13 1525A Cont&Recirc Spray 123Bl 11448-FH-lOlA 11448-FP-13 548/\\

Cont&Recirc Spray 123Cl 11448-FH-lOlA 11448-FP-13 547 Cont&Recirc Spray 123Dl 11448-FH-101/\\

11448-FP-13 546/560 Cont&Recirc Spray 123El 11448-FH-lOlA 11448-FP-13 546/560 Cont&Recirc Spray 123E2 11448-FM-lOlA 11448-FP-13 562 Cont&Recirc Spray 123Fl 11448-FH-lOlA 11448-FP-13 562 Cont&Recirc Spray 123F2 11448-FH-lOlA 11448-FP-13 54615620 Cont&Recirc Spray 123F3 11448-FH-lOlA 11448-FP-13 54616500 Cont&Recirc Spray l23Gl 11448-FH-lOlA 11448-FP-13 544 Cont&Recirc Spray 123G2 11448-FM-lOlA 11448-FP-13 544 Cont&Recirc Spray 123Hl 11448-FM-101 11448-FP-13 548B Cont&Recirc Spray 123H2 11448-FH-101 11448-FP-13 548C Cont&Recirc Spray 123Jl 11448-FH-101 11448-FP-5, 60 7441754 Cont&Recirc Spray 123Kl 11448-nf-1o1 11448-FP-5, 60 745 Cont&Recirc Spray 123Nl 11448-FH-101 11448-FP-60 751 Cont&Recirc Spray 123N2 11448-Hf-101 11448-FP-60 751 Cont&Recirc Spray 123Rl 11448-FH-101 11448-FP-13 544B Cont&Recirc Spray 123R2 11448-FH-101 11448-FP-13 544A Cont&Recirc Spray A-2

~Llll

SURRY POYER STATION, UNIT 1 APPENDIX A CCont)

CROSS REFERENCE OF MKS, FM, FP, PROBLEM NO., SYSTEM MKS FM FP Problem System ll 7Al 11448-FM-104 11448-FP-12 508 Residual Heat RHVL 117A2 11448-FM-104 11448-FP-12 508 Residual Heat RMVL 117Bl 11448-FH-104 11448-FP-3, 12 540 Residual Heat RHVL 124Al 11448-FH-103 11448-FP-9 630 Pressurizer Spray/Relief 124A2 11448-FH-103 11448-FP-9 630 Pressurizer Spray/Relief 125Al 11448-FM-103 11448-FP-9 636 Pressurizer Spray/Relief 137Al 11448-FM-85.

11448-FP-19, 20, 74 CVl Containment Vacuum 137A2 11448-FH-85 11448-FP-19, 20, 74 CVl Containment Vacuum 143Al Not Applicable 11448-FB-25 1040 Diesel Muffler Exhaust 144A 11448-FB-45A 11448-FB-3 CFl Fire Protection 144B 11448-FB-45A 11448-FB-3 CF2 Fire Protection 11.-3 no

I SURRY POWER STATION, UNIT 1 I

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APPENDIX B I

CORRESPONDENCE WITH NRC I

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I SURRY POWER STATION, UNIT 1 APPENDIX B CORRESPONDENCE WITH NRC The following is a

listing of correspondence with the NRC related to the reanalysis effort.

Item

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Date Signature 1

3/13/79 Denton 2

Stello 3

4/13/79 Stello 4

5/18/79 Stello 5

Eisenhut 6

7/18/79 O'Reilly 7

8/15/79 O'Reilly 8

8/27/79 Denton 9

10/ 5/79 O'Reilly 10 10/23/79 Murphy 11 10/24/79 Murphy 12 10/25/79 Murphy 13 ll/15/79 Eisenhut 14 3/30/79 Spencer Addressee Letter No./Subject NRC TO VEPCO Pz-offitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Proffitt Show Cause Order Addendum to Show Cause Order Use of Soil Structure Interaction Techniques Request for Further SSI Information Factor Adjustment to SSI Calculated Stresses Information Pertaining to I.E.

Bulletin No. 79-14, Revision 1 Letter of Guidance on I.E. Bulletin No. 79-14 Lifting of Suspension Required by the Order to Show Cause Confirmation of Concurrence Refers to NRC Inspection of Sept. 10-13 and Sept. 19-21, 1979 Refers to NRC Inspection of Sept. 13-14, 1979 Refers to NRG Inspection of Sept. 26-28, 1979 Refers to Soil Structure *Interaction VEPCO TO NRG Denton/

Stello 198/Initial Response to Show Cause Order B-1

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I Item

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Date 15 4/19/79 16 17 18 19 5/2/79 20 5/2/79 21 5/22/79 22 23 24 6/5/79 25 26 27 6/12/79 28 29 6/l 9/79 30 6/25/79 31 8/l/79 32 8/21/79 SURRY POWER STATION, UNIT 1 APPENDIX B CCONT)

CORRESPONDENCE WITH NRC Signature Addressee Letter No./Subject Stallings O'Reilly Spencer O'Reilly Spencer O'Reilly Spencer Denton/

Stello Stallings Denton Spencer Stello Ragone Hendrie Spencer Stello Spencer Stello Spencer Denton Spencer Denton Spencer Stello Spencer Denton Spencer Denton Spencer Denton Spencer Denton Spencer Denton Spencer Denton 270/LER 79-0l0/0l3L-0 289/Response to I.E. Bulletin No. 79-07 288/Response to I.E. Bulletin No. 79-07 311/Transmittal to Two Sample Problems to EG&G Observations on Reanalysis Effort 260/Submittal of SSI Information Comments on Moratorium/Surry Reanalysis Response to NRC Letter of 4/2/79 Response to NRC Letter of 5/18/79 Submittal of Report on Reanalysis Additional Information, Report on Reanalysis of Piping Soil Structure Interaction Report Modification Information, Reanalysis of Piping Systems Schedule and Support Information Support Modifications Support Information, Reanalysis of Piping Systems Submittal of Revised Report on Analysis Analysis Completion of Designated Supports - Outside Containment B-2

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I SURRY POWER STATION, UNIT 1 APPENDIX B CCONT)

CORRESPONDENCE WITH NRC Item

~

Date Signature Addressee Letter No./Subject.

33 10/4/79 Spencer 34 10/3/79 Proffitt 35 10/4/79 Spencer 36 10/15/79 Spencer 37 11/28/79 Spencer 38 12/7/79 Spencer 39 12/13/79 Spencer 40 12/21/79 Spencer 41 3/22/79 Kennedy 42 Jacobs 43 4/3/79 Jacobs 44 Kennedy 45 4/6/79 Jacobs 46 4/ll/79 Jacobs 47 Jacobs 48 Jacobs 49 4/27/79 Jacobs 50 Jacobs 51 Rossier O'Reilly Response to NRC Letter of 7/2/79 Denton Seismic Analysis of Piping Systems O'Reilly Response to I.E. Letter Dated 9/7/79 O'Reilly Extension of I.E.Bulletin 79-14 Deadline Denton Seismic Analysis of Piping Systems O'Reilly I

Response to NRC Letter of ll/8/79 Denton Show Cause Order Reanalysis O'Reilly Show Cau~e 60 Days Analysis Completion S&W TO NRC Denton Herring Bezler Denton

Stello Bezler Transmittal of S&W Computer Programs Submittal of Computer Outputs Submittal of Benchmark Problem to Brookhaven National Laboratory Transmittal of S&W Computer Programs Plan for Verification of Dynamic Analysis Codes Submittal of Computer Outputs Stello Update and Status of Verification Plan for Dynamic Analysis Codes Hartman Submittal of Computer Outputs Bezler Submittal of Benchmark Problems Stello Status of Verification Plan for Dynamic Analysis Codes Neighbors Draft Outline of SSI-ARS Report B-3

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Item

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52 53 54 55 56 57 Date Signature 519179 Kennedy 5111179 Kennedy 5114/79 Kennedy 614179 Jacobs 6112/79 Jacobs 916179 Allen SURRY POWER STATION, UNIT 1 APPENDIX B CCONT)

CORRESPONDENCE WITH NRC Addressee Letter No./Subject Stello Reference SHOCK 0 Program Stello Reference SHOCK 0 Program Denton Proprietary Computer Codes Bezler Submittal of Benchmark Problems Bezler Submittal of Benchmark Problems Stello Response to NRC Letter of 8/10179 B-4

ML18136A394

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ML18136A394

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Dear Mr. Denton:

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