ML19296C290
| ML19296C290 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/22/1980 |
| From: | EBASCO SERVICES, INC. |
| To: | |
| Shared Package | |
| ML18138A045 | List: |
| References | |
| NUDOCS 8002250537 | |
| Download: ML19296C290 (81) | |
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REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS SURRY POWER STATION-UNIT 2 VIRGINIA ELECTRIC AND POWER COMPANY EEN [lll8L FEBRUARY 22,1980 EBASCO SERVICES INCORPORATED JERICHO, NEW YORK 800225053'7 _ _ _ . . _ . . . .
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Ve co _ _ _ _ _ _ _ February 22, 1980 Mr. Harold R. Denton Serial No. 138 Office of Nuclear Reactor Regulation PSE&C/CMRjr:L/ wang U.S. Nuclear Regulatory Commission Washington, DC 20555 Docket No. 50-281 License No. DPR-37
Dear Mr. Denton:
START UP REQUEST SURRY POWER STATION UNIT 2 The purpose of this letter is to request start-up of Surry Power Station Unit 2 af ter installation of certain piping system modifications identified in the attached " Report on the Reanalysis of Safety Related Piping Systems, Surry Power Station, Unit 2", dated February 22, 1980. The basis of this start-up request is the confidence of system operability during the seismic events associated with the Design Basis Earthquake (DBE) and the Operating Basis Earthquake (OBE). The attached report documents the final results of all aspects of the analysis associated with the Nuclear Regulatory Commission Order to Show Cause of March 13, 1979 for Surry Power Station Unit 2. Modifications are identified in the report relating to the stress analysis of piping systems and pipe support evaluations. Our request for start-up is based on the following:
- 1. Completion of pipe stress reanalysis and resulting modifications installed for all stress problems originally run on the Shock II computer program.
_ 2. Completion of detailed support analyses and resulting modifications - installed for Shock Il problems inside the containment structure.
- 3. Completion of detailed support analyses and resulting modifications installed on the SHOCK II port:ons of the following four systems outside the containment structure:
- a. Low Head Safety Injection
- b. High Head Safety Injection
- c. Containment Spray
- d. Auxiliary Feed Water System Completion of the above work was the basis for interim operation of Unit 1 while analysis continued on systems outside the containment other than the four safe shutdown systems noted above. The Unit 2 work includes analysis to both the DBE and OBE load cases, whereas only the DBE load case was completed for Unit 1 at the time of interim operation.
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In addition to that stated above, a substantial amount of work has been or will be completed beyond that required for interim operation of Unit 1. The additional work that will be completed prior to start up of Unit 2 is as follows:
- 1. Completion of pipe stress ar Ilys,s and resulting modifications installed for all I.E. Bulletin 79-14 pipe stress problems inside the I containment.
- 2. Completion of detailed support analyses and resulting modifications installed for all I.E. Bulletin 79-14 lines inside the containment.
- 3. An on going effort for I.E. Bulletin 79-02 involving inspecting and I testing one accessible anchor bolt per base plate and analyzing base plates and anchor bolts for flexibility. All work inside the containment will be completed and 80% of the work outside the containment will be completed prior to start-up.
Compl< " ion of the above items represents a substantial milestone in the overall analysis effort. All piping and supports analyzed and modified as a I result of the Show Cause and IE Bulletin 79-14 analyses are capable of performing their intended function without experiencing an overstrecsed condition. All modifications associated with the above items will be I completed prior to start up of the Unit following the steam generator replacement outage. At the present time, it appears that these modifications can be completed in May, 1980 depending on the modification installation rate our field forces are to able to attain. The remaining work to be completed after start-up will be completion of the support analysis and any modifications that might be required on the I remaining systems outside tSe containment for both Show Cause and IE Bulletin 79-14. The reporting process for significant modifications will follow the procedure outlined in our letter of November 28,1979 (Serial No. 972). We would appreciate your prompt review and approval of our request for returning Unit 2 to service. We believe that the analytical work completed and the modifications installed at the time of start-up provides a high degree I of confidence that the integrity of safety systems for Unit 2 can be assured during the DBE or OBE events. The remaining analytical and modification work outside the containment will be expedited during the operation of the Unit. Very trulyfyours,
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f/f[ g W. C. Spencer I Vice President - Power Station Engineering and Construction Services Attachment cc: Mr. Victor Stello, Director Office of Inspection & Enforcement I Mr. James P. O'Reilly, Director Office of Inspection & Enforcement, Region II
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__ a _ SURRY POWER STATION - UNIT 2
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_- REPORT ON Tile REANALYSIS OF SAFETY-FELATED PIPING SYSTEMS SURRY POWER S'J ATION - UNIT 2 VIRGINIA ELECTRIC AND POWER COMPANY FEBRI?ARY 1980
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EBASCO SERVICES INCORPORATED JERIC110, NEW YORK v
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__ SURRY POWER STATION - UNIT 2 _ TABLE OF CONTENTS Section Title Page 1.0 S UMMARY AN D CO NC LU S ION S . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 2.0 SCOPE OF REANALYSIS............................. 2-1 3.0 P I P E ST RE S S RE S U LT S . . . . . . . . . . . . . . . . . . . . . . . . .... 3-1 4.0 PIPE SUPPORT RESULTS............................ 4-1 5.0 SCHEDULE FOR COMPLET10N......................... 5-1 6.0 H I GH E N E RGY LI NE B RE AK S . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 7.0 C0NSERVATISMS....................... ........... 7-1 7.1 Field Verification of As-Built Conditions..... 7-1 7.2 Quality Assurance and Engineering Assurance. . 7- 1 7.3 Use of Amplified Response Spectra............. 7- 1 7.4 Conservatisms Applied to Inertial Stress...... 7- 2 8.0 SYSTEM OPE RABILITY EVALUATION. . . . . . . . . ......... 8-1 9.0 BRANCH LINE
SUMMARY
.............. .............. 9-1 10.0 RESPONSE TO THE NUCLEAR REGULATORY COMMISSION'S CONCERNS......... ............. .. 10-1 10.1 Support Stiffness................ .......... . 10-1 10.2 NUPIPE Computer Code...................... ... 10-1 10.3 Problem 2538 - Support H-15................... 10-1 10.4 Benchmark Problems............................ 10-2 Appendix A Systems Affected........................... .... A-1 B Flow Diagrams - Identification of Problems Analyzed B-1 C Response to IE Bulletin 79-04................... C-1 D Correspondence with the NRC..................... D- 1 1- i
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_ . _ . . . . . . . _ _ SURRY POWER STATION - UNIT 2 LIST OF TABLES Table Title 3-1 PIPE STRESS RE-EVALUATION
SUMMARY
3-2 N0ZZLE AND PENETRATION
SUMMARY
3-3 PIPE STRESS HARDWARE MODIFICATION
SUMMARY
3-4 HARDWARE MODIFICATION
SUMMARY
DUE TO N0ZZLE AND PENETRATION OVERLOADING 4-1 PIPE SUPPORT ANALYSIS
SUMMARY
4-2 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
5-1 SCHEDULE FOR COMPLETION 1-il - _ . . . .
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SURRY POWER STATION - UNIT 2 SECTION 1
SUMMARY
AND CONCLUSIONS In response to the Nuclear Regulatory Commission's Order to Show Cause, dated March 13, 1979, a reanalysis was conducted of safety related piping systems for Surry Power Station Unit 2 which were originally dynamically analyzed using the Sil0CK 2 computer program. The S110CK 2 program, which used an earlier load combination methodology, is no longer considered ac-ceptable by the NRC. This report discusses the details of the analysis work and results of the pipe and support analyses within the scope of the reanalysis for Surry Unit 2. Further, this reanal; sis is consistent with the methods used on Surry Power Station Unit 1, which were discussed in earlier reports submitted on June 5, 1979 (Vepco Serial No. 453) and on August 1, 1979 (Vepco Serial No. 453A) and on January 15, 1980 (Vepco Serial No. 048).
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This reporc summarizei the total reanalysis effort for all aspects of the March 13, 1979 Orier to Show Cause for Surry Power Station Unit 2. All piping systems affe ted by the Order to Show Cause, both inside and outside the containment, have been reanalyzed using the NUPIPE program, which is acceptable to :he NRC. Table 3-3 (Pipe Stress Hardware Madi-fication Summary) and Table 3-4 (Hardware Modification Summary Due to Nozzle and Penetration Overloading) identifies all modifications to the piping systems which have resulted from this reanalysis. While some of these modifications are attributable to the seismic analysis method, the majority of modifications result from differences in the as-built conditions and other miscellaneous reasons. All of these modifications have been or will be made prior to startup of the unit following the steam generator replacement outage. With the installation of these modifications, all Surry Unit 2 piping within the scope of this report will meet the Final Safety Analysis Report (FSAR) allowables for both the Operating Basis Earthquake and Design Basis Earthquakes (OBE and DBE) conditions. All pipe supports inside the containment and all supports outside the containment for the High Head Safety Injection, Low Head Safety Injection System, Containment Recirculation Spray and Auxiliary Feedwater Systems affected by the Order to Show Cause have been evaluated for the revi9ed supp- rt loads from the pipe stress reanalysis. All of these hardware modifications have been or will be installed prior to start up of the Unit following the steam generator replacement outage. Table 4-2 (Pipe Support Hardware Modification Summary) reports all the modifications resulting from the support reanalysis. As was the case in the piping system reanalysis, most of the modifications are the result of differ-ences between the original design conditions and the actual field as-built condition. For the remaining supports outside the containment, other than those four systems listed above, modifications are expected to be completed in June 1980. 1- 1 -- _ _ _ . . . . . . , ,
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_ SURRY p0RER STATION - UNIT 2 During the reanalysis of Surry Unit 2, 79 pi pe stress modifications and 256 pipe suppo rt modi fic a t ions were ident i fied ; while 63 pipe st ress and 66 pipe support modifications were identified on Surry Unit 1. The dt f fe rences in the number of modifications is not considered significant, d ue to the conduct of the reanalysis applied to Surry Unit 2. Modifica-tions on Surry Unit I were iden t i fied af ter many anal yt ic al iterations; whereas, on Surry Unit 2 modifications were designed based on fewer iterations. The conduct of the reanalysis in this manner served to identify modifications faster so that systems could be upgraded more quickly in order not to substantially interfere with the completion of tha Steam Generator Replacement Project. In addition, the Surry Unit 2 reanalysis included the OBE condition. Further, all pipe supports were as-built in the field and QC verified prior to reanalysis. Lastly, to limit the interface problems between the Show Cause scope and other piping, supports were added to facilitate the NUPIPE reanalysis. Any overstressed condition ident i fied during the reanalysis of the remaining supports outside the containment, for which the loads exceed one-half the ultimate capacity of the support, will be reported to the NRC and appropriate actions taken as required by the Technical Speci-fication, as de sc ribed in Section 8 of this report Based on the result s of the analysis of supports done to date, it is not expected that any significant number of the remaining supports should have a sa fe ty factor of less than two with respect to ultimate capacity. , h 1- 2
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_ SURRY F0WER STATION - UNIT 2 SECTION 2 SCOPE OF REANALYSIS As desc ribed tn the NRC Order to Show Cause, March 13, 1979, some piping systems in the Surry Power Station, Unit 2 were dynamically analyzed with a S110CK 2 computer program that is not currently acceptable to the NRC.
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All systems or portions of systems that were analyzed by the SHOCK 2 c omput e r program have been identified in Appendix A. These systems were reanalyzed by Stone & Webster Engineering Corporation (Stone & Webster) and Ebasco Services Inco porated (EBASCO) using a NUPIPE com-puter code. Responsibility fo - the reanalysis is also ident i fied in Appendix A by system and problem number. The results of the reanalysis are c om pa red with code allowable pipe stresses, allowable loads for nozzles and penetrations, and are used in the evaluation of pipe supports.
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__ _ SURBY POWER STATION - UNIT 2
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SECTION 3 _ PIPE STRESS RESULTS
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A total of 62 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 are being analyzed by two groups: Stone & Webster Engineering Corporation (Stone & Webster) in Boston, Massachusetts, and Ebasco Services Incorpora-tion (EBASCO) in Jericho, New York, as indicated in the following table: PIPE STRESS PROBLEMS Stone & Webster EBASCO Total
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13 49 62 Responsibility for the reanalysis is identified by system and problem number in Appendix A of this report. Field-verified piping isometric drawings provide the basis for program in-puts for the pipe s*.ress reanalysis. 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 (SRSS) technique which is always more conservative than the approved SRSS method, and an SRSS technis a for inter-modal combination. ~ Piping is analyzed in most cases utilizing amplified response spectra (ARS) that are developed using soil structure interaction techniques (SSI-ARS). The resultant stresses and loads are used to evaluate piping, supports, j nozzles, and penetrations. In accordance with the NRC letters of May 25, 1979 and November 15, 1979 to Virginia Electric and Power Company (VEPCO), the seismic inertial stresses and loads computed using the SSI-ARS have been increased by a factor of 1.5 for the DBE and 1.25 for OBE conditions. All 62 problems have been reanalyzed. Table 3-1, Pipe Stress Re-Evaluation Summary, presents the results for these 62 stress problems. In Table 3-1, 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 original design stress isometrics (MSK's).
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In Table 3-1, 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 the NUPIPE computer runs with the seismic inertial stress multi-plied by a factor of 1.5 and then added to the Seismic Anchor Movement (SAM) Stress for runs using the SSI-ARS. Even though Table 3-] reports DBE results, stress analysis is performed for OBE also and modifications de-signed wherever necessary.
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The Original Total and Original Seismic Stresses shown in Table 3-1 were computed using the SHOCK 2 programs for the original design conditions. The New Total and New Seismic stresses were computed by the NUPIPE pro-3-1
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SURRY POWER STATION - UNIT 2 gram using different mass models and in most cases different ARS's than the - original calculations. More importantly, the reanalyses were based on as-built conditions, field verified in 1979, which in some cases differ from the original design conditions. For these reasons, the new stresses __ and the original stresses in Table 3-1 are not comparable, as they do not necessarily represent the same physica'. conditions. Table 3-2, Nozzle and Penetration Summary, summarizes the nozzles and pene-trations evaluated u'nder the reanalysis program. For all the problems in which the SSI-ARS are used, the seismic inertial nozzle loads have been increased by a factor of 1.5 for DBE per the NRC letter of May 25, 1979, and by a factor of 1.25 for OBE per the NRC letter of November 15, 1979. Table 3-3, Pipe Stress liardware Moditication Summary, lists the hardware
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modifications necessary to bring the pipe stress analysis to within code allowables. Of the 62 problems reanalyzed, hardware modifications were made to 16 problems due to pipe stress. These modifications consisted of 22 added, modified, or deleted supports. The modifications include those
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necessary to the flexibility analysis of the branch lines. A branch line (Problem No. 2508) was rerouted as a result of thermal reanalysis, not as a result of seismic reanalysis. Table 3-4, Hardware Modification Summary due to Nozzle and Penetration Overloading, lists all modifications to reduce nozzle and penetration loads. Of the 62 problems reanalyzed, hardware modifications were made to 17 problems due to nozzle overload. These modifications consisted of 57 added , modi fied , or deleted supports. Those modi ficat ions which result from the piping reanalysis are identified in Section 3. Only the modifications which result from the pipe support reanalysis are reported in Table 4-2, Pipe Support liard ware Modification ~ Summa ry . Final verification of piping and support stresses, and Engine-ering Assurance review has yet to be completed for a few problems. It is expected, however, that the number and type of modifications due to the stress and support analysis are correc t and final. _ 3-2
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SURRY POWER ST ATION - CNIT 2 TABLE 3-1 Sheet 1 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name Line Size Pice Stress (psi) and Reanalysis MKS NPS Original Original New New Problea Number
- Responsibility Number (Inches) Total Seismic Total Seismic Allowable Low Head Safety Injectica 2555 E 122D1 10,12 12043 NA 7974 2449 30690 2709 E 122L1 12 NA NA 19173 11427 33750 2537/2540/25403 E 122Al, 4,b, 12350 NA 2739 883 33750 11781 10,12 2539 E 122J1 6 30368 NA 14771 7330 32985 2727 S&W 127C1 6 21179 NA 24352 17453 33750 127C2 8,10 2081 E 127K1 8 1677 307 1220 185 2B485 2682 E 127K2 S 1677 307 1174 164 28485 2695 E 127DI 8 21179 NA 2094 1103 26485 2697 E 127D2 8 21179 NA 1961 1022 28435 High Head Safety Injection 2689 E 127F1 10 24049 NA 11773 9571 33750 2735 E 127G1 3,4,b, NA NA 26660 17772 33750 127C2 8,10 Containment and Recirculation sprav 2521 S&W 123Al 8,10- 14904 NA 7790 4276 33561 2523 S&W 123A2 8,10 14904 KA 7977 6013 33561 2547 S&d 123Cl 8,10 12713 hA 23532 19739 33561 2546 E 123D1 8,10 3528 1576 8992 7328 2EF00 2541 E 123D2 8,10 3528 1576 18338 16635 28600 2542 E 123D3 8,10 3526 1576 16931 17252 25d00
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w '- ummum - m ugums ummus - m m a SURRY POWEk STATION - thlT 2 TABLE 3-: Sheet 2 of 5 PIPE STRESS RE-EVALCATION
SUMMARY
System Name Line Size Pipe Stress (psi) and Reanalysis MKS NPS Original Original New New Problem Number Responsibility Number (Inches) Total Seismic Total Seismic Allowable Co n t ainme nt and Re-circulation Spray (Cont'd) 2543 E 123D4 8,10 3528 1576 6498 6988 29970 2560 E 123El 10 7334 NA 12775 10995 29970 2561 E 123E2 10 7334 NA 6587 3576 29970 2544 E 123G1 10 11605 7922 2912 1181 26485 2533 E 123G2 10 11605 7922 5674 3813 28485 2548 E 123H1 10 15785 11241 3904 2437 29970 2545 E 123H2 10 15785 11241 2397 676 29970 2744 E 123J1 8 7966 5118 16143 15167 35320 2745 E 123K1 8 24643 22577 15621 12559 33750
?753 E 123L1 12 6136 2816 1344 394 33750
'.754 E 123M1 12 5649 NA 1999 949 33750 2751 E 123N1 10 6010 NA 21234 13842 28485 2752 E 123N2 10 6010 NA 18613 13934 2E455 2549 S&W 123C2 8 11955 10125 10081 8397 33561 2755 E 123P1 4,8 10369 6324 14311 7340 33750 2756 E 123Q1 10 NA NA 5705 2666 28455 2757 E 123Q2 10 5810 NA 3S47 2381 2e485 Main Steam 2577 S&W 100D1 30 13624 NA 10763 2MM3 33750 2558 S&W 101D1 30 18635 NA 12513 3041 33750 2579 S&W 102D2 30 13031 NA 11434 4120 33750 2346* S&W 103Al 30 19970 NA 3256S 25477 33750 103A2
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-- W -' m ' M - M N N M M SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 3 of 5 PIPE STRESS RE-EVALUATION SL'MMARY System Name Line Size Pipe Stress (psi)
__ and Reanalysis MKS NPS Origir 1 Original hew New Problem Number Responsibility Number (Inch .s Total Seismic Total Seismic Allowable Feedwater 2569 S&w 100G1 14 14499 NA 13681 9360 27000 2573 S&w 101CI 14 16025 NA 12970 8376 27000 2571 S&w lo2G1 14 17927 NA 14230 8443 27000 Auxiliary Feedwater 2473 F ll8Al 3,6 8568 2407 20963 17736 27000 ll8A2 2683 E II8cl 4,6 21230 NA 12988 9188 27000 I!8C2 Pressurizer Spray 2771 E 125Al 4 18560 NA 8013 3088 30b90 Pressurizcr Sa fety and Re! . T 2000 E 124A1 3,4 9093 NA 8824 5421 30636 124A2 6,12 Residual Heat Removal 2540/2540B E Listed Under Low Head Safety Injection System 2508A/2508B E Il7Al 10,12,14 NA NA 13112 8461 24570 2554 E 117C1 6 NA NA 12003 8824 29970 Service Water 2465 E .19Al 24 NA NA 6529 6212 21600 2467 E Il9A2 24 NA NA 6561 6214 21600 - - - - - ___
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SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 4 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name Line Size Pipe Stress (psi) and Reanalysis MKS NPS Original Original New New Problem Number Responsibility Number (Inches) Seismic Total Total Seismic Allowable Service Water (Cont'd) 2469 E Il9A3 24 NA NA 14687 13730 21600 2471 E Il9A4 24 NA NA 12459 11614 21603 Component Cooling 2601/2603 E 112S1 18 9696 NA 7043 5246 21600 112S2 2604/2605 E ll2AAI 18 9696 NA 7074 5204 21600 ll2ABI Containment Vacuum 2650 S&W 137Al 8 25,750 NA 13659 13037 21600 HP Steam to Auxiliary Feedwater Pump 2869/2862/2864 E 131A1 3,4 22609 NA 24229 19559 27000 131B1 131C1 _ . . . .
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SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 5 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
Legend: E = E B ASCO S&W = Stone & Webster NA = Not Applicable Allowabic Stress = 1.8 S h New Total Stress (for SSI/ARS) =5 LP , sDW + '"$ 3DBEI , 3DBEA
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New Seismic (for SSI/ARS) = 1.5 S DBEI
- 3DBEA New Total Stress (original ARS) =SLp + SDW
+SDEEI
- bDEEA New Seismic (original ARS) =S DBEI Where S p = Longitudinal Pressure Stress S = Dead Load Stress DW SD3EI = Seismic Inertial Stress, Design Basis Earthquake S
DBEA = Se smic Stress due to Anchor Movements, Design Basis Earthquake S h
- All wable stress at maximum (hot) temperature Note:
The original total and original seismic stresses shown in Table 3-1 were computed using SHCCK ? for the original design conditions. The new total and new seismic stresses were computed by the NUPIPE program using dif ferent mass models and, in most cases, different ARS's than the original calculations. More importantly, the reanalyses were based on field-verified, as-built conditions in 1979, which, in some cases, dif fer significantly from the original design conditions. For this reason, the new stresses and the original stresses in Table 3-1 are not comparable, as they do not necessarily represent the same physical conditions.
- Soil Structure Interaction (SSI) Amplified Response Spectras (ARS) were used in the new analysis for all problems except Problem 2346 which utilizes a combination of SSI-ARS and the original ARS.
- Problems having / are counted as separate problems example: 28b9/2862/2864 are counted as three problees. Usine this method of counting the total number of pipe stress problems equal 62.
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SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 1 of 4 N0ZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems Vendor
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Re s po n s i-System bility Total No. No. Ac c r.p t ab le Nozzle Con f i rma t ion and Fo r of Nozzles / (Evaluation Mod i f ic at ion Being Problem No. Analysis atmetrations Complete) Required Obtained Low Head Safety Injection 2555 E 1/0 1 0 1
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2709 E 1/0 1 0 0 2537/2540 E 1/0 1 0 1 2539 E 0/0 NA NA NA 2727 S&W 2/0 2 0 2 2681 E 0/0 NA NA NA 2682 E 0/0 NA NA NA 2695 E 0/0 NA NA NA 2697 E 0/0 NA NA NA High Head Safety Injection 2689 E 0/0 NA NA NA 2735 E 3/0 3 0 3 Containment and Recirculation Spray 2521 S&W 0/0 NA dA NA 2523 S&W 0/0 NA NA NA 2547 S&W 0/0 NA NA NA _ 2546 E 0/0 NA NA NA
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SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 2 of 4 N0ZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems Re s pon s i- Vendor I System bility Total No. No. Acceptable Nozzle Confirmation and Fo r of Nozzles / (Evaluation Mod i f ic at ion Being Problem No. Analysis Penetrations Complete) Required Obtained Containment and Recirculation Spray (Cont'd) 2541 E 0/0 ta NA M 0/ 0 NA NA M 2542 E NA NA 2543 E 0/0 NA 0 0 2560 E 1/0 1 1/0 0 0 2561 E 1 1/0 0 0 2544 E 1 1/0 0 0 2533 E 1 . 1/0 0 0 2548 E 1 1/0 0 0 2545 E 1 0/0 in NA fa 2744 E 0/0 NA NA !M 2745 E 1/0 0 0 2753 E 1 _ 2754 E I/0 1 0 1 2751 E 2/0 2 0 0 2752 E 2/0 2 0 0 2549 S&W 0/0 NA NA NA 2/0 2 0 2 2755 E 2/0 2 0 0 2756 E 2/0 2 0 0 2757 E
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C_ SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 3 of 4 N0ZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems Re s pon s i- Vendor System bility Total No. No. Acceptable Nozzle Confirmation and Fo r of Nozzles / (Evaluation Mod i f ic at ion Be ing Problem No. Analysis Penetrations Complete) Required Obtained Main Steam 2577 56W 1/1 1/1 0/0 0/0 2588 SsW 1/1 1/1 0/0 0/0 2579 S&W 1/1 1/1 0/0 0/0 2346 S&W 0/0 NA NA NA Feedwater 2569 S&W 1/1 1/1 0/0 0/0 2573 S&W 1/1 1/1 0/0 0/0 2571 S&W 1/1 1/1 0/0 0/0 Auxiliary Feedwater 2473 E 0/0 NA NA R\ 2683 E 3/0 3 0 3 Pressurizer Spray 2771 E 1/0 1 0 1 Pressurizer Safety and Relief 2000 E 5/0 5 0 5 Residual lleat Removal 2540 E (Listed under Low Head Safety Injection System) - - - _ _ _ _ . . . . . . .
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SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 4 of 4 N0ZZLE AND PENEIRATION
SUMMARY
Slf0CK 2 Problems Responsi- Vendor System bility Total No. No. Acceptable Nozzle Confirmation and For of Nozzles / (Evaluation Modification Being Problem ho. Analysis Penetrations Complete) Required Cbtained Residual Heat Removal (Cont'd) 2540B E 0/0 NA NA NA 2508A/2506B E 8/0 8 0 8 2554 E 0/0 NA NA NA Service Water 2465 E 1/0 1 0 0 2467 E 1/0 1 0 0 2469 E 1/0 1 0 0 2471 E 1/0 1 0 0 Component Cooling 2601/2603 E 2/0 2 0 1 2604/2605 E 2/0 2 0 1 Con t a i nme r.t l Vacuum 2650 S&W 0 NA NA NA IIP Steam to Auxiliary Feedwater Pump 2662/2864/2869 E 1/0 1 0 0 1 NOTES: NA = Not Applicable E = EBASCO 56W = Stone & Webster i 1
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--. . y .. . . m y y m y y m SURRY POWER STATION - 1 NIT 2 TABLE 3-3 Sheet i of 2 PIPE STRESS HARDWARE MODIFICATION SlHMARY System Name Reanalysis MKS At t ribut ed and Problem No. Overstressed Condition To: Kenolution No. of Modi ficat ions Responsibility h low Head Safety Injection 2709 E 122L1 Seismic overstress Seasmic Sprang hange r replaced 1 Reanalysts by rigid rentraint.
122Al Removed a restratnt, 2 2537/2540 E Thermal overat ress As-bunit 117B1 anchor replsced by restraints and a snubber. 2539 E 122J1 Thermal overst ress As-boalt Rex,oved a restratnt I 122KI (Branch Line) Containment and Recirculation Sprav 2549 S&W 123C2 Pape cont act s c rane Seismic Lateral support added. I wall during seismic Reanalysis cenditaon. 2544 E 123GI Th e rma l ove rs t re s s As-built Fev ved a rentraant. I 2745 E 123K1 Seismic anchor move- As-built Vert ic al rest raint s 2 ment overstress replaced by sprang hangers at two loca-tsans 2752 E 123N2 Thermal overstress As-built Remaved a rest raa nt . 1 (Branch Line) Pressurizer Spray 2771 E 125Al Sei wir overstress As-bunit Two re<traints added. 2 Residual Heat Bemoval 2508 E Il7Al Thermal overstres. As-busit Rerootang of I-l/2 in. 1 Eranch lane pace 254. (List ed under Low Head Safety In ject ion System) _ _ _ . _ _ _ . . _ . . .
w- M ---- -' - ' ' m 'm m m m m m m m m SURRY POWER STATION - UNIT 2 TABLE 3-3 Sheet 2 of 2 PIPE STRESS HARDWARE MODIFICATION
SUMMARY
System Name Reanalysis MKS Attributed and Problem No. Responsibility No. Overstressed Condition To: Resolution No. of Modifications Residual Heat Removal (Cont'd) 2540B E ll7B Thermal and seismic As-built Anchor replaced by 2 overstress vertical restraint, horizontal restraint removed. Component Cooling 2604/ E Il2AAl Se ismic overstress Se i smic Two restraints added. 2 2605 ll2ABI Reanalysis HP Steam to Auxiliary Feedwater Pump 2862/ E 131A1 Thermal and seismic As-built / Two anchors replaced 5 2864/ 131B1 overstress Seismic by restraints, two 2869 131CI Reanalysis snubbers and a spring added. Feedwater 2569 S&W 100G1 Insufficient br a rre h As-built Remove existing 1 line flexibility U-bolt on 3/4 in, line Notes: E = EBASCO S&W = Stone & Webster ' - - - -
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_ _ _ . __ .. . SURRY POWER STATION - UNIT 2 TABLE 3-4 Sheet 1 of 2 HARDWARE MODIFICATION
SUMMARY
DUE TO NOZZLE AND PENETRATION OVEHLOADING System Name Reanalysis Attributed and Problem No. Responsibility Equipment No. To: Resolution No. of Modifications Law Head Safety I'nj ec t ion 2555 E 2-SI-TK-1B As-built / Two restraints 2 Seismic added. Reanalysis High Head Safety injection 2735 E 2-CH-P-I A Scismic Ten restraints added, 13 2-CH-P-1B Reanalysis one vertical restraint 2-CH- P-I C replaced by spring hanger, two anchors added Containment and Recirculation Spray 2544 E 2-RS-E-ID As-built One rest raint removed 1 2533 E 2-RS-E-!C As-built Two restraints added 2 2753 E 2-CS-P-IB As-built / One vertical rest raint 3 Seismic raplaced by sprina Reanalysis hanger, two restraints added 2754 E 2-CS-P-IA As-buil t / One vert ic al restraint 2 Seismic replaced by spring Reanalysis one horizontal restraint added. 2751 E 2- R S-P-2 A Seismic One restraint added 1 Reanalysis 2752 E 2-RS-P-2B Seismic One restraint added 1 Reanalysis 2755 E 2-CS-P-I B As-built / One restraint added 3 2-CS-P-IA Seismic t wo vert ical restraints Reanalysis removed. 2756 E 2-RS-E-1A As-built One anchor and one 2 2-RS-P-lA restraint removed _._..
-- N M M M-'- M ' ' W W W W W W W W SURRY POWER STATION - UNIT 2 TABLE 3-4 Sheet 2 of 2 HARDWARE MODIFICATION
SUMMARY
DUE TO N0ZZLE AND PENETRATION OVEkLOADING Sy s t em Name Reanalysis Attributed and Problem No. Responsibility Equipment No. To Resolution No. of Modifications Containment and Recirculation Spcay (Cont'd) 2757 E 2-RS-E-1B As-built One anchor removed 1 2-RS-P-1B Auxiliary Feedwater 2683 E 2-FW-P-2 Seismic Three horizontal 5 2-FW-P-3B Reanalysis and two vertical 2-FW-P-3A restraints added. Pressurizer Safety & Relief 2000 E 2-RC-TK-2 As-built A spring replaced 4 by a rigid hanger and a horizontal snubber, two restraints replaced by snubbers, lateral restraint deleted. Residual Heat kemoval 2508h E 2-RH-P-1A Seismic Six snubbers added, two 10 2-RH-P-1B Reanalysis springs replaced by restraints, one spring hanger added, one vertical restraint added. Service Water 2471 E 2-RS-E-ID As-built One restraint removed 1 Component Cooling
;601/2603 E 2-Ril-E-1 B As-built Four ve rt ic al rest rainc u 6 Seismic replac ed by springs and Peanalysis snubbers, two rest raint s added.
Not e: E = EBASCO - - - - - _ _ . _ _ . . . . . .
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SURRY POWER STATION - UNIT 2 SECTION 4 PIPE SUPPORT RESULTS Table 4-1, Pipe Suppo rt Analysis Summary, summarizes the pipe support Six hundred four (604) supports, (427 inside the con-
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reanalysis program. tainment, 177 outside the containment) on lines originally analyzed using Shock 2, were reanalyzed as part of this Show Cause e f fort . Two hundred fifty six (256) hardwa re modifications have been identified. The modifications identified due to the pipe support reanalysis are listed in Table 4-2, Pipe Support Hardware Modi fication Summary. Those modifications which result from the piping reanalysis are identified in Section 3. Only the modifications which result from the pipe support reanalysis are reported in Table 4-2. Of the modifications identi fied ,
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only 104 were the result of seismic reanalysis of the piping systems identi-fled in the Show Cause Order, while 152 were the result of di f ferences ident t f ted between the as-built conditions and the original design. These __ condttions are identified in the table for each problem. For all the problems in which the SSI-ARS are used, the seismic inertial loads have been increased by a factor of 1.5 for DBE per the NRC letter of May 25, 1979, and by a factor of 1.25 for OBE per the NRC letter of November 15, 1979. __ m 4-1
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SURRY POER STATION - UNIT 2 TABLE 4-1 Sheet 1 of 4 PIPE SUPPORT ANALYSIS
SUMMARY
System Name Total Modifications and Analysis Number of Evaluation or Additions Problem Number Responsibility Location Supports Complete Required Low Head Safety Injection System 2537/2540 E IC 33 33 16 IC 17 17 8 2555 E 2539 E IC 7 7 5 2681 E OC 4 4 3 OC 5 5 3 2682 E E OC 9 9 4 2695 CC 9 9 6 2697 E IC 9 9 3 2709 E 2727 S&W OC 17 17 10 High Head Safety Injection Sy9cem E OC 5 5 4 2689
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2735 E OC 48 48 21 Containment and kecirculation Spray S&W IC 15 15 4 2521 S&W IC 16 16 5 2523 Ssw IC 13 13 6 2547 S&W IC 4 4 1 2549 2546 E IC 11 I1 8 - __.
E -- M ' ' M M M M M M M M -- SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 2 of 4 PIPE SUPPORT ANALYSIS
SUMMARY
Total Modifications System Name Analysis Number of Evaluation or Additions and Complete Required Problem Number Responsibility Location Supports Containment and Recirculation Sp g (Cont'd) 11 6 E IC 11 2541 11 II 4 E IC 2542 11 6 E IC 11 2543 3 3 2 E IC 2560 5 3 g IC 5 2561 0 2 E IC 6 2544 5 1 E IC 5 1533 15 7 E IC 15 2548 II 9 E IC 17 2545 E N 4 2744 OC 4 4 1 E 2745 4 4 I E OC 2753 3 1 E OC 3 2754 5 1 E OC 5 2751 4 4 0 E OC 2752 10 10 4 E OC 2755 E C 2756 10 3 E IC 10 j 757
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SUMMARY
System Name Total Modifications and Analysis Number of Evaluation or Additions Problem Number Responsibility Location Supports Complete Required Main Steam S&w Ic 9 9 2 2577 S&W IC 2 2 0 2588 S&W IC 5 5 3 2579 S&w OC 41 41 6 2346 Fe er. . il e r, Ssw IC 9 9 4 2569 S&w IC 3 3 0 2573 2571 S&W IC 6 > 1 Auxiliary Feedwater E IC 34 34 10 2473 E OC 22 22 7 2683
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Pressurizer Spray l and Relief l 32 7 j 2771 E IC 32 E IC 31 31 15 2000 Residual Heat Removal E IC 47 47 4 2508A/B E IC 5 5 5 2540B J 0 2554 E OC 1 1
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SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 4 of 4 PIPE SUPPORT ANALYSIS
SUMMARY
System Name Total Modifications and Analysis Number of Evaluation or Additions Problem Number Responsibility Location Supports Complete Required Service Water 2465 E IC 2 2 1 2467 E IC 2 2 1 2469 E IC 2 2 0 2471 E IC 2 2 1 Component Cooling 2601 E IC 16 16 5 2603 E IC 13 13 4 2604 E IC 16 16 8 2605 E IC 17 17 3 Containment Vacuun 2650 S&W DC 3 3 2 liigh Pressure Steam to Aux Feedwater Pump 2862 E OC 12 12 1 2864 E OC 3 3 0 2869 E OC 7 7 1 Notes: E = EBASCO S&W = Stone & Webster IC = Inside Containment OC = Outside Containment - - - - - - _ _ . . . . . . .
M "- W W W W M M M M W SURRY PCWER STATION - UNIT 2 TABLE 4-2 Sheet I of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMEER RESPONSIBILITY LOCATION NUMBER MODIFICATION To: RESOLUTION Low liead Saf ety Injection System 2537/2540 E IC 2537 E IC 2.4 Loc al pipe wall stress Seismic Modify support exceeds allowable reanalysis 6 Support member over allowable As-built Modify support 2540 E IC 5 Insufficient clearance Seismic Modif y support Reanalysis 7,8,9,10,12, Support member over As-built Modif y support 13,26 allowable 28 Pipe clamp over allowable As-built Madif y support 17,19 U-bolt over allowable As-built Modif y support 1 Support member over allowable As-built Modify support
&A Upward vertical restraint Se ismic Modify restraint required reanalysis for uplift load 2555 E IC 8,16 Support member over allowable As-built Modif y support 3 Weld over allowable As-built Add weld 4,5 Local pipe wall stress exceeds Seismic Modif y support allowable reanalysis 9,12 Support member over allowable seismic Modif y support 12A Upwsrd vertical re straint Seismic Modify restraint req u ir ed Reanalysis for uplift load 2539 E IC 2 Upwsrd vertical restraint Seismic Modify restraint required Reanalysis for uplift load i Upward vertical restraint Seismic Modif y restraint required Reanalysis for uplift load 1** Support member over allowable As-built Modify support 3,4 Support member over allowable As-built Modify support
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- g. y SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 2 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE RESPONSIBILITY LOCATION NUMBER MODIFICATICN TO: RESOLUTION PROBLEM NUMBER Low Head Safety Injection System (Cont'd) 2709 E IC 7 bupport member over allowable As-built Modify support 2,3 Local pipe wall stresses over Seismic Modify support allowable Reanalysis 2727 S&W OC 8 Support over allowable Seismic Modify Support Reanalysis 13 Support and weld over Se i smic Modif y Support allowable Remnalysis 11 Loads out of range of spring As-built hep lac e spring 14 Loads out of spring range Se ismic Replace spring Reanalysis 15 Loads out of spring range Se ismic Re p l ace spring Heanalysis
' - Loads out of spring range Seismic Replace spring keanalysis 18 Loads out of spring range Seismic Replace spring Reanalysis 19 Support restrains lateral As-built Modif y support movement E OC H-1,H-17 Weld over allowable As-built Add weld 1695 E' OC H-50 Support member over allowable As-built Modify support A-16 Support member over allowable As-built Modify support C-53 Support member over allowable As-built Modify support A-17 Support member over allowable As-built Modif y support
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- m '- " w ' W w m m muur uumm' W W SURRY POWdR STATION - UNIT 2 TABLE 4-2 Sheet 3 f 12 PIPE SUPPORT 11ARDWARE MODIFINTION
SUMMARY
MKS SYSTEM NAME ATTRIBUTABLE ANALYSIS SUPPORT REASON FOR AND TO: RESOLUTION LOCATION NUMBE R MODIFICATION PROBLEM NUMBER RESPONSIBIL ] Low Head Safety Injection System (Cont'd) H-49 Support member over allowable As-built Modif y support 2697 E OC Support not acting As-built Eemoved support C-7 C-17,C-18 Support member over allowable As-built Modify support Support raumber ove r allowable As-built Modify support A-14 Support member over allowable As-built Modity support A-15 2,4 Support me.nbe r ove r allowable As-built Mod if y support 2681 E OC 5 U-bolt over allowable As-built Modify support 4 Support member over allowable As-bailt Modify support 2632 E OC 2 Support trember over allowable As-built Modify support 5 C-bolt over allowable As-built Modify support High Head Safety injection System E OC C-38,C-39 Support member over allowable A9-built Modif y support 2689 C-40,C-41 Support member over allowable As-built Modif y support OC 22,37,45,28 Support member over allowable As-built Modify support
'735 4 E 36,21,23,44 1,3,16,31,39,24 Weld over allowable As-built Add weld 4,6,18,33,41,56 U-bolt over allowable Seismic Modify support 26 Local pipe wall stress Seistic Modif y support exceeds allowable reanalysis Containment and Recirculation Spray IC 2 U-bolt capacity for side- Seismic Add raembers to 2521 S&W load is insufficient Reanalysis resist sidelcad
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....- y .. y y y y SURRY POWER STAT 10N - UNIT 2 TABLE 4-2 Sh'*l O Of I2 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS ANALYSIS SUPPGRT REASON FOR ATTRIBUTABLE AND LOCATION MODIFICATION TO: RESOLUTION PROBLEM NUMBER RESPONSIBILITY NU MBE R Containment and Recirculation Spray (Cont'd) Frame overstressed with Se ismic Modify existing 2521 S&W IC 3 new loads out of springs Reanalysis f rame and replace range As-built springs 4 U-strap has insufficient Seismic Replace existing capacity Reanalysis strap with new framing 5 Local stress Seismic Elimi.. ate anchor Reanalysis and add ver./lat restraint S&W IC U-bolt capacity for side- Seismic Add members to 2523 1 load is insufficient Reanalysis resist sideload 2 Frame overstressed Se ismic Replac e. existing Heanalysis frame As-built 3 Capacity of springs in- Seismic Replace springs sufficient Reana ly s is 4 U-strap has insufficient Seismic Replace existing capacity heanalysis strap with new framing 5 Local stress Se ismic Eliminate anchor Reanalysis and add vert /lat
- restraint S&W IC 2 Lateral load fails U-bolt As-built Add lateral 2547 restraint 4 Rod hanger cannot resist Seismic Replace with upward load Reanalysis sway strut 6 Insufficient clearance As-built Remove lateral for the rmal movement stop 8 Insufficient lateral As-built Remove lateral clearance for thermal stops (angle) mo vemen t
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SURRY POWER STATION - UNIT 2 TABLE 4-2 Sbett 5 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOn ATT RIBUTAB LE PKOBLEM NUKBER RESPONSIBILITY LOCATION NUMBER MODIFICATION _ To: RESOLUTION Containment and Recirculation Spray ( Cont ' d ) 2547 S&W IC 10 Insufficient lateral As-built Remove lateral clearance f or thermal stops (angle) movement 11 Local stress and support As-built Modify structure frame overstressed 2549 S&W IC 2 U-bolt failure As-built Add lateral restraint 2546 E IC 6 Support member over allowable As-built Modify suppcrt 9 Insufficient lateral & Seismic Modify restraint vertical clearance heanalysis 7,8 Insufficient lateral Seismic Modify restraint clearance Reanalysis 22,26 Support member over allowable As-built Modify support 2 U-bolt restricts lateral As-built Modify support movement 22A Anchor st ress over allowable Seismic Relocate adjacent heanalysis restraint 2541 E IC 6,21 Support member over allowable As-built Modity support 7,9 Insufficient lateral Seismic Modif y support clearance Reanalysis 2 U-b o l t restricts lateral As-built Modify support movements 22 Support member over allowable As-built Modify support 2542 E IC 15,23 Support membe r ov e r allowable As-built Modify support 13,17 Insufficient lateral clearance Seismic Modif y support Reanalysis
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_ _ _ _ ... . . . . SURRY POWEk STATION - UNIT 2 TABLE 4-2 Sneet 6 of 12 PIPE SUFPORT HAFDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR AITRIbUTABLE RESPONSIBILITY LOCATION MODIFICATION TO RESOLUTION PROBLEM NUMBER NUMBdR_ Containment and Recirculation Spray 2543 E IC 15,23 Support member As-built Modify support over allowable 12,13,14 Insufficient lateral Seismic Modify restraint clearance Reanalysis 24A Support member Se ismic Relocate adj a-over allowable Reanalysis cent restraint 2560 E IC H-49A Support member As-built Modify support over allowable IF50 0-bolt over Seismic Modif y support allowable Reanalysis 2561 E IC H-9 ] Upward vertical Seismic Modif y for restraint required Re ana lys is uplift load IF49B Support member As-built Modify support over allowable H-98A Support member As-built Remove vertical over allewable restraint 2544 E IC H-67 Upward vertical Seismic Modif y support restraint required Re an a l y s i: for uplift load H-68 Support member As-built Modify support over allowable 2533 g IC H-3 Support member As-built Modify support over allowsble 2548 E IC 7 Support member As-built Modify support over allowable 10 Support member As-built Modif y support over allowable 12 U-bolt over As-built Modif y support allowable 9A Upward vertical Seismic Modif y support restraint required Reanalysis for uplift load - - - - - _ _ _ . . . . .
.. -.-- . . SURRY PO4ER STATION - UNIT 2 TABLE 4-2 Sheet 7 of 12 PIPE SUPPORT HARDWARE MCDIFICATION
SUMMARY
SYSTEM MAME MKS AND ANALYSIS SUFFORT REASON FOR ATTRIBUTABLE RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION PROBLEM NUMBER Containment and Recirculation Spray (Cont'd) 2548 E IC 11 Support member As-built Modify support over allowable 6,8 Support member As-built Modify support over allowable 2545 E IC 3 Support member As-built Modif y support over allowable 14 Upward vertical Seismic Modif y restraint restraint required heanalysis for iplift load 2 U-bolt over As-built Modify support allowable 4 Support member As-built Modify support over alloweble 7 Support member As-built Modify support over al low ab le 10,15 Weld over allowable As-built Add weld 6,8 Support member As-built Modify support over allowable E OC 2,3 Loads out of spring As-built Two rigid re-2744 range straints re-placed by springs 1 Weld over allowable As-built Add weld 2745 E OC 4 Upward vertical Seismic Modif y support restraint required Reanalysis 275) E OC 2 Local pipe wall Seismic Modif y support stress over Reanalysis allowable 2753 E OC 1 Support member As-built Modif y support over allowable 2754 E OC 1 Support member As-built Modif y support over allowable _ _ _ . . .
- M - 'M ' ' W W W M M M M W SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 8 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM HKS AND ANALYSIS SUPPORT REASON FOR ATIRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) 2755 E OC 7,8 Upward vertical Seismic Modif y support restraint required Reanalysis for uplift lo ad 9 Upward vertical Seismic Radesign support restraint required Reanalysis for uplift load 11 Weld over allowable As-built Add weld 2756 E IC 54,55 Support member At-built Modif y support over allowable 2'i$7 E IC H-90 Upward vertical Seismic Modif y support for restraint required Reanalysis uplift lo ad H-53, Support member As-built tbdify support 11 - 8 8 over allowable Main Steam 2577 S&W IC 1 Local stress ex- As-built Modify lug ceeds allowable 9 Local stress ex- An-built Re place lug with ceeds allowable clamp 2579 S&W IC 1 Spring variability Seismic Re place spring ratio exceeded Reanalysis 4 Loads outside Seismic Replace spring spring range Reanalysis 5 Spring variability Se ismic Replace spring ratio exceeded. Reanalysis Replace pipe lug Local stress over with clamp, allowable. 2346 S&W OC 1,2,3 Loads outside spring Seismic Re p lace springs, range, local over- Reanalysis modify lug stress in lug 5,7,9 Snubbers, local Seismic Modify snubbers stress, a nd s u p- Reanalysis and lugs port members are overstressed -- _ _ _ . . _ . _ . _ . . . . _ .
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.. y y SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 9 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITT LOCATION NUMBER MODIFICATION TO RESCLUTION Feedwater 2569 S&W IC 2,3 Loads out side spring Se i smi c Replace springs range Reanalysis 6 Thermal movement As-built Reduce pin-to pin dimension 7 Insufficient clearance The rma l . Madify support for lateral movement Movement 2571 S&W IC 5 Loads outside spring Seismic Replace springs range Reanalysis Auxilicry Feedwater 2473 E IC 8 Lateral clearance in- Se i smic Modify sufficient Reanalysis restraint 14 Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 16 Upward vertical rest raint Seismic hodify restraint required Reanalysis for uplift load 11,13,26,29,32 Weld over allowable As-built Modify support 22 Support member over As-built Modify support allowable 28 Support member over As-built Modify support allowable 2683 E OC H-2,P-8A U-bolt over allowable As-built Hodify support H-Il U-bolt over allowable As-built Modify support H-9 Support member over As-built Modify support allowable H-1,H-5 Local pipe wall stress Seismi- Modify support over allowable Reanalysis H-4 U-bolt over allowable As-built Modify support by adding bracing raemb e r s _ _ _ _ _ _ _ . .
_ . _ . _ .. . . SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 10 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBFR RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Pressurizer Spray and Relief 2771 E IC 33 Upward vertical restraint Seismic Modif y support required Reanalysis for uplift load 5,23 Weld over allowable An-built Add weld 6 Support member over As-built Hodify support allowable 26,27 Upward vertical restraint Seismic Modif y for uplif t required Reanalysis lo ad 32 Insufficient lateral Seismic Modify support clearance Re an a l y s is 2000 E LC 4,12,H-5 Locil Pi Pe well stress Seismic Modif y support over allowables Reanalysis 15 Insufficient ve rtic al Seismic Modify support clearance Reanalysis 13 Support restraints lateral As-built Modify support movement 4A,7,8,H-1A, Support member over As-built Modify support 10,II,2]A,ll3 allowable 17 Support member over As-built Modif y support allowable 2 Weld over allowable As-built Add weld 2508 E IC H-36,H-15,H-17 Support member over As-built Modify support allowable H-12 Vertical support not Se i smic Remove support required Reanalysis 2540(B) E IC 20,21 Uplift vertical restraint Se i smic Modif y f or uplitt required Reanalysis lo ad -- - . _ _ . .
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SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 11 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NU MBER MODIFICATION TO RESOLUTION Pressurizer Spray and Relief (Cont'd) 2540(B) E IC 22 Support member over allowable As-built Modify support 3,25 Local pipe wall stress over Seismic Modify support allowable Reanalysis Service Water 2465 E IC 1 Support member over As-built M7dify support allowable 2467 E IC 1 Support member over As-built Modif y support allowable 2471 E IC 2 Local pipe well stress Seismic Modif y support over allowable Reanalysis Component Cooling 2601 E IC H-32A.H-28,H-44 Uplift vertical Se ismic Modif y support for restraint required Reanalysis uplift H-30 Insufficient la t e r a l Seismic Modif y support clearance Reanalysis R-31 Weld over allowable As-built Add weld 2603 E IC 4 Insufficient lateral clear- Seismic Modify support ance Reanalysis 6 Support member over allowable As-built Modify support 9 Upward vertical restraint Se ismic Modify support for required keanalysis uplift lo ad 10 Upward vertical restraint Se ismic Modif y support for required keanalysis uplift l o ad 2604 E IC H-38A Upward vertical restraint Seismic Modify support for required keanalysis uplift load H-38B Upward vertical restraint Seismic Hodify support for required Reanalysis uplift load . . . .
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w w--mmr -- - w - - - - ummuur SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 12 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUIABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Component Cooling (Cont'd) 2604 E IC H-35,H-36,H-23, Weld over allowable As-built Add weld H-38C H-38 Support member over allowable As-built Modify support H-38D Local pipe wall stress Seismic Modify support exceeds allowable Remnalysis 2605 E IC H-25 Support member over allowable As-built Modify support H-25B Upward vertical restraint Seismic Modify support for required Reanalysis uplift lo ad H-25A Upward vertical restraint Seismic Modif y support for required Reanalysis uplift lo ad Containment Vacuum 2650 S&W OC 1 Support restraint lateral As-built Modify support movement 2 Local stress at at- As-built Move support above tachment on pipe elbow and use double exceeds allowable trunnion Q h Pressure Steam To Aux. Feedwater Pump 2862 E OC 3 Support member over An-built Modif y support allowable 2 3 W) E OC 5 Support member over An-built Modify support allowable Notes:
** Originally Problem No. 2708
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__ SURRY POWER STATION - UNIT 2 SECTION 5 SCilEDULE FOR COMPLETION The status of the reanalysis of those systems subject to Show Cause and the installation of modifications identified as being required by the reanalysis is shown in Table 5-1, Schedule for Completion. ' Reanalysis on all systems is complete pending final review. Any required modifications on lines inside containment and on the liigh Head Safety In-jection, Low Head Safety Injection, Containment Recirculation Spray, and Auxiliary Feedwater Systems will be installed prior to startup of the Unit following the steam generator replacement outage. Installa tion of modifica-tion on the balance of systems outside containment is expected to be com-piete in June 1980. 5- 1 __ _ _ _ _ _ . _ . . . . _ .
-- g g-- g g g g g g g g g SURRY POWER STATION - UNIT 2 TABLE 5-1 Sheet 1 of 1 SCHEDULE FOR COMPLETION Status Reanalysis Stress Support / Restraint Modification Location of Problem Responsibility Reanalysis Reanalysis Installation Inside Containment Systems E/S&W Complete Complete Prior to start-up following SGR outage Outside Containment Systems Low Head Safety Injection E/S&W Complete Complete Prior to start-up following SGR outage High Head Safety Injection E Complete Complete Prior to start-up following SGR outage Containment Recirculation Spray E Complete Complete Prior to start-up following SGR outage Auxiliary Feedwater E Complete Complete Prior to start-up following SGR outage Balance of Systems E/S&W Complete Complete Complete by June, 1980 NOTES: E = EBASCO S&W = Stone & Webster SGR = Steam Generator Replacement
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__ SURRY PtWER STATION - UNIf 2 SECTION 6 HIGH ENERGY LINE BREAKS For the high energy lines outside the containment addressed in Appendix D of the Final Safety Analysis Report (FSAR), only the main steam lines are included in this stress reanalysis. Each of the main steam lines has two terminal break locations, one at the containment penetration and the other at the main steam manifo'. Each of the risers to the main steam relief valve headers has two tert.inal break locations, one at the main ste am line s, the other at the tee into the main s teen header . These terminal breakpoints are predetermined and are not changed as a result of the stress reanalysis. Two intermediate break locations were originally determined based upon maximum primary plus secondary stresses. Upon reanalysis, two additional breakpoints on each of the steam lines were located. One of these points is located immediately upstream of the check valve and the other point is at the elbow j ust downstream of the check valve. All of these points will be included in the augment ed inservice inspection program. 6-1 - - - .
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SURRY POWER STATION - UNIT 2 SECTION 7 CONSERVATISMS The conservatisms applied to the design of the piping systems for Surry Power Station Units 1 and 2 were extensively delineated in Section 7 of the VEPCO June 5, 1979 submittal (Serial Number 453). The seismic capability of nuclear piping and the seismic event probability at the Surry Power Station were discussed in that submittal. The design of Unit 2 closely follows the design of Unit 1, applying the same conservative criteria with respect to safety systems and system redundancies. Similiarly, the reanalysis efforts on Surry Power Station Unit 2 closely follows that of Unit 1, applying the same stress limits and soil struc-ture interaction amplified response spectra (SSI-ARS). Paragraphs 7.1, 7.2, 7.3 and 7.4 describe the differences in the conser-vatisms applied to the Unit 2 reanalysis. - 7.1 FIELD VERIFICATION OF AS-BUILT CONDITIONS To ensure that the pipe stress and pipe support reanalysis is performed as accurately as possible, field verification of as-built conditions has been performed. The field verification produced detailed piping isometric drawings and pipe support sketches for each support upon which reanalysis is based. All field-verified piping isometrics and pipe support sketches
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are independently verified by Surry Power Station quality control personnel. 7.2 QUALITY ASSURANCE / ENGINEERING ASSURANCE 7.2.1 EBASCO QUALITY ASSURANCE The EBASCO Ql Topical Report ETR-1001, Revision 7, as approved by the Nuclear Regulatory Commission on December 15, 1978, is being applied to the Surry Unit 2 reanalysis activities. 7.2.2 STONE & WEBSTER QUALITY ASSURANCE / ENGINEERING ASSURANCE The Stone & Webster Quality Assurance program described in the VEPCO June 5, 1979 submittal to NRC, is being applied to the Surry Unit 2 reanal-ysis activities. i 7.3 USE OF AMPLIFIED RESPONSE SPECTRA The use of amplified response spectra was extensively discussed in the June 5, 1979 submittal. The soil structure interaction amplified response Spectra (SSI-ARS) are being used in the reanalysis in most cases. For pipe runs extending over a range of elevations S&W and EBASCO utilized an amplified response spectra enveloping the acceleration of the mass points spanning the elevation of the piping run. 7-1
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_ . _ __ SURRY POWER STATION - UNIT 2 7.4 CONSERVATISMS APPLIED TO I"rRTIAL STRESSES - In accordance with the NRC letters of May 25, 1979 and November 15, 1979 to VEPCO, the seismic inertial stresses and loads computed using the SSI-ARS have been increased by a factor of 1.5 for the DBE and 1.25 for OBE conditions. 7-2
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,, . . _ _ _ _ - - , -.
SURRY POWER STATION - UNIT 2 SECTION 8 SYSTEM OPERABILITY EVALUATION When an analysis is complete, the following procedura will be used in the decision making process as to the reportability to the NRC, including de-termination of system non-operability status of over-stressed supports / restraints. If a potential support modification is identified, a check is made to de-termine if the new load is greater than 50 percent of the ultimate capacity of that support. A parallel effort is initiated whereby a preliminary support modification is designed and the preliminary support modification is sent to the site. If the new load is greater than 50 percent of ultimate, the station manager is notified of a potential nonconformance. If the station manager deter- - mines a nonconformance exists and if the preliminary modification has not been installed, then the Technical Specification governs. If the new load is less than 50 percent of ultimate, the support is expedi-tiously installed af ter any nonconformances have been corrected. _ 8-1 _. - -
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SURRY POWER STATION - UNIT 2 SECTION 9 BRANCH LINE
SUMMARY
Branch lines are evaluated to assure that sufficient flexibility exists between the run pipe and the first few restraints on the branch piping. The flexibility of the branch pipe must be evaluated separately in each of the three translational directions and must be sufficient to prevent overstresses in the branch /run pipe interface due to thermal and seismic displacements imposed on the branch pipe. The procedure is intended to provide a secondary stress check based on run pipe displacements result-ing from the current analysis. If a branch line is part of the scope of work under 1.C Bulletin 79-14, a detailed evaluation is performed as part of the IE 79-14 effort. E6W has performed evaluation of branch lines in accordance with Section 6 of the August 1, 1979 report for Unit 1 (Vepco Serial No. 453A). EBASCO has per fo rmed evaluation of some of the branch lines by coding for the NUP1PE program and analyzing it for seismic anchor movement and thermal analysis. Engineering judgement is used in qualifying the branch lines with small displacements in the remaining cases. Thermal analysis is conducted by applying the thermal displacements from the run pipe and the operating temperature of the branch line. The seismic anchor movement analysis is pe r f o rmed by applying seismic inertia displacements. The applicable stress intensification factor (S1F) at the branch connection is included in the analysis. The stresses from both analyses are combined by absolute sum. Allowable stress i9 considered to be SA* l 1 I I j e.1 _ _ _ . . . . . . . . . .
_ . .__.
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2 SURRY POWER STATION - UNIT 2 SECTION 10 RESPONSE TO NRC STAFF CONCERNS A meeting was held with the Nuclear Regulatory Commission at Ebasco Services, Jericho Offices on October 24, 1979, to review pipe stress analyses within EBASCO's scope of work. As a result of the discus-sions, four staff concerns were identified as delineated in the NRC Summary of Meeting Notes dated November 13, 1979. These concerns were:
- 1) The validity of support stiffness used in the piping reanalysis whe1, for example, a vertical trunion is welded onto a horizontal wide flange.
- 2) The pertinence of the version of B31.1 Code implemented in Control Data Corporations' NUPIPE program, which was used in the 3BASCO reanalysis program.
- 3) The identification of the original loads on support H-15 in problem 2538.
"
- 4) The verification of the NUPIPE computer program (benchmark problems).
These concerns are addressed in the following sections. 10.1 SUPPORT STIFFNESS The original piping analysis of Surry Unit 2 did not consider the actual stiffness of the supports. Representative support stiffness was considered during the current reanalysis. During the pipe support reanalysis effort it has been observed that cer-tain anchor type supports expose wide flange members to torsional moments. This type of loading condition results in a very flexible support. As a part of the pipe support reanalysis effort, anchors have been reviewed for this type of leading and members modified to resist torsion as required. 10.2 NUPIPE COMPUTER CODE At EBASCO's request, Nuclear Services Corporation (NSC) conducted a thorough review of the NUPIPE program against the source codes, NSC has determined that all values utilized by the program, but not spec-ified by the user as input, are pertinent to the 1967 and earlier versions of the B31.1 Power Piping Code. The code of record for Surry Unit 2 is B31.1 1955 with code class N-7. 10.3 PROBLEM 2538 - SUPPORT H-15 Problem 2538, a portion of the Low Head Safety Injection System (LHSIS) was originally analyzed as a hand calculation by S&W; SHOCK 2 was not used, therefore, problem 2538 is not within the scope of the Show Cause Order. In the original analysis, decal loads were applied to the re-straints in this problem. These decal loads did not include moments. 10-1 _ .. .
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SURRY POWER STATION - UNIT 2 In the EbASCO NUPIPE analysis of the portion of the LilSIS within pro-blem 2538, the system was not overstressed. Ilowever, the loads iden-tified by the NUPIPE analysis as exi3 ting at hanger 15 caused local pipe wall and support anchor stresses to exceed allowables by an order of magnitude. Support H-15 has been modified so that it will relieve the local overstress conoitions. 10.4 BENCliMARK PROBLEMS EBASCO has pe r fo rmed four pipe stress problems supplied by the NRC to verify the NUPIPE computer progran. The results were submitted to the staff in the EBASCO letter to Dr M lla rt zman dated January 3, 1980 (Letter Number VEP/NRC/002). _ 10-2
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_ _ _ SURRY POWER STATION - UNIT 2
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.. APPENDIX A SYSTEMS AFFECTED " A-1 ---'M - - . . . . .
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_ SURRY POWER STATION - UNIT 2 The reanalysis included those safety related lines originally computer-analyzed with the SHOCK 2 program. Th e systems line numbers, the associated computer problem numbers, and the flow diagram numbers are listed below. The following table includes all seismically analyzed lines. Th e figure numbers re-fer to the FSAR drawings, and the Surry Unit 2, FM and FB drawings included in Appendix B. = Re s po n s i- Flow bilities Problem MKS Diagram System Line No. for Analysis No. No. No. Low Head 8-SI-214-153 E 2695 127D1 FM-106A Safety 8-SI-292-153 E 2697 127D2 FM-106A Injection 8-SI-214-153 E 2681 127K1 FM-106A 8-SI-292-153 E 2682 127K2 FM-106A 10-SI-284-152 S&W 2727 127C1 FM-106A 10-SI-216-153 S&W 2727 127C1 FM-106A 8-SI-292-153 S&W 2727 127Cl FM-106A 10-SI-351-153 S&W 2727 127C1 FM-106A 6-SI-249-1502 S&W 2727 127C1 FM-106A I 10-SI-349-153 S&W 2727 127C1 FM-106A
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8-SI-214-152 S&W 2727 127C1 FM-106A 10-SI-283-152 S&W 2727 127C2 FM-106A 10-SI-213-153 S&W 2727 127C2 FM-106A 6-SI-248-1502 S6W 2727 127C2 FM-106A 10-SI-352-1502 S&W 2727 127C2 FM-106A 10-SI-350-153 S&W 2727 127C2 FM-106A 10-SI-349-153 S&W 2727 127C2 FM-106A 10-SI-348-153 S&W 2727 127C2 FM-106A 8-SI-214-153 S&W 2727 127C2 FM-106A 12-SI-247-602 E 2537 122Al FM-106B 12-SI-247-1502 E 2537 122'1 FM-106B 12-RC-324-1502 E 2537 122Al FM-106B 10-RH-ll7-1502 E 2537 122A1, FM-106B, ll7B1 104A 12-SI-246-602 E 2555 122D1 FM-106B 12-Si-246-1502 E 2555 122D1 FM-106B 12-KC-323-1502 E 2555 122D1 FM-106B 10-RH-116-1502 E 2555 122D1 FM-106B 6-SI-248-1502 E 2539 122K1 FM-106B 6-SI-249-1502 E 2539 122K1 FM-106B 6-SI-250-1502 E 2539 122J1 FM-106B 6-RC-321-1502 E 2539 122J1 FM-106B 6-SI-343-1502 E 2539 122K1 FM-106B 12-SI-245-602 E 2709 122L1 FM-106B 12-SI-245-1502 E 2709 122L1 FM-106B 12-RC-322-1502 E 2709 122L1 FM-106B High Head 10-SI-206-153 E 2689 127F1 FM-106A Safety 6-CH-372-152 E 2735 127G1 FM-105B Injection 4-CH-412-152 E 2735 127G1 FM-105B 3-CH-373-152
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E 2735 127G1 FM-105B 8-SI-214-153 E 2735 127G2 106A A-2
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_- _ ._ SURRY POWER STATION - UNIT 2 Responsi- Flow __ bilities Problem MKS Diagram
- ysten Line No. for Analysis No. No. No.
High Head 8-CH-504-152 E 2735 127G1, G2 105B Safety 8-Cll-317-152 E 2735 127G1, G2 105B _ Injection 8-SI-217-152 E 2735 127G1, G2 106A (Cont'd) 8-SI-292-153 E 2735 127G1 106A 6-SI-218-152 E 2735 127G1, G2 105B, 106A 6-SI-219-152 E 2735 127G1, G2 105B, 106A 6-SI-278-152 E 2735 127G1, G2 105B, 106A 6-CH-501-152 E 2735 127G1 105B 6-CH-502-152 E 2735 127G1 105B 6-C11-503-15 2 E 2735 127G1 105B 8-CH-505-152 E 2735 127G2 105B 8-CH-506-152 E 2735 127G1, G2 105B _ 8-SI-207-152 E 2735 127G2 106A 8-SI-302-152 E 2735 127G2 106A
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8-SI-170-153 E 2735 127G2 106A 8-SI-172-153 E 2735 127G2 106A 10-SI-206-153 E 2735 127G2 106A 6-CH-318-152 E 2735 127G1 105B 6-CH-319-152 E 2735 127G1 105B Re s id ua l 14-Ril-101-1502 E 2508 ll7Al FM-104A Heat Removal 14-Ril-10 2-602 E 2508 ll7Al FM-104A 10-RH-104-602 E 2508 117Al FM-104A 10-Ril-105-6 02 E 2508 ll7Al FM-104A 12-Ril-106-602 E 2508 Il7Al FM-104A 10-Ril-107-602 E 2508 Il7Al FM-104A 10-Ril-108-602 E 2508 ll7Al FM-104A
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10-Rll-109-602 E 2508 Il7Al FM-104A 10-RH-Il0-602 E 2508 ll7Al FM-104A _ 12-Ril-l l 2-602 E 2508 Il8Al FM-104A 14-RH-118-602 E 2508 117Al FM-104A 12-Ril-119-602 E 2508 Il7Al FM-104A 12-RH-ll2-602 E 2540 117B1 FM-104A 3-Ril-113-602 E 2540 117B1 FM-104A 4-Ril-l l 5-152 E 2540 ll7B1 FM-104A 10-Ril-ll6-1502 E 2540 117B1 FM-104A 10-Ril-l l 7-1502 E 2540 117B1 FM-104A 6-Ril-120-152 E 2540 11781 FM-104A 10-Ril-13 7-602 E 2540 ll7B1 FM-104A 6-Ril-120-152 E 2554 117C1 FM-104A, 101A A-3 _
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I SURRY POWER STATION - UNIT 2 Responsi- Flow bilities Problee MKS Diagram System Line No. for Analyeis No. No. No. Main Steam 30-SHP-102-601 S&W 2588 101D FM-14A 30-SHP-102-601 S&W 2588 101D FM-14A I 30-SHP-103-601 30-SHP-101-601 30-SHP-102-601 S&W S&W S&W 2579 2346 2346 102D 103A 103A FM-14A FM-14A FM-14A 30-SHP-103-601 S&W 2346 103A FM-14A 30-SHP-124-601 S&W 2346 103A FM-14A 30-SHP-123-601 S&W 2346 103A FM-14A 30-SHP-122-601 S&W 2346 103A FM-14A Feedwater 14-WFPD-117-601 S&W 2569 100G FM-18A 14-WFPD-113-601 S&W 2573 101G FM-18A 14-WFPD-109-601 S&W 2571 102G FM-18A Auxiliary 6-WAPD-101-601 E 2473 118A1, A2 FM-18A,18B Feedwater 6-WAPD-102-602 E 2473 Il8A2 FM-18A,18B 3-WAPD-109-601 E 2473 118Al, A2 FM-18A 3-WAPD-110-601 E 2473 ll8A1, A2 FM-18A 3-WAPD-111-601 E 2473 118A1, A2 FM-18A 3-WAPD-Il2-601 E 2473 118A1, A2 FM-18A 3-WAPD-ll3-601 E 2473 ll8Al, A2 FM-18A 3-WAPD-ll4-601 E 2473 118Al, A2 FM-18A 6-WAPD-150-601 2473 118A1, A2 FM-18A,18B I E 6-WAPD-151-601 E 2473 ll8Al, A2 FM-18A,18B 6-WAPD-101-601 E 2683 ll8G2 FM-18A,18B 6-WAPD-102-601 E 2683 118G1 FM-18A,18B I 6-WAPD-103-601 6-WAPD-104-601 4-WAPD-105-601 E E E 2683 2683 2683 118G1, G2 Il8G1, G2 118G1, G2 FM-18A FM-18A FM-18A I 4-WAPD-106-601 4-WAPD-107-601 4-WAPD-108-601 E E E 2683 2683 2683 ll8G1, G2 118G1, G2 ll8G1, G2 FM-18A FM-18A FM-18A 6-WAPD-50 601 E 2683 118G1, G2 FM-18A,18B 6-WAPD-52-601 E 2683 ll8G1, G2 FM-18A,18B Service Water 24-WS-126-10 E 2465 119Al FM-21A I 24-WS-128-10 24-WS-130-10 24-WS-132-10 E E E 2467 2469 2471 119A2 119A3 119A4 FM-21A FM-21A FM-21A I I I I A.4 g 4
SURRY PliWER STATION - UNIT 2 Re s pon s i- Flow l11 bilities Problem MKS Diagram System Line No. for Analysis No. No. No. Pressur ize r 4-RC-334-1502 E 2000 124A1 FM-103B Safety and 3-RC-335-1502 E 2000 124A1 FM-103B Relief 3-RC-361-1502 E 2000 124A1 FM-103B I 6-RC-320-602 6-RC-362-602 12-RC-336-602 E E E 2000 2000 2000 124A1, A2 124A1, A2 124A1, A2 FM-103B FM-103B FM-103B I 6-RC-337-1502 6-RC-338-1502 6-RC-339-1502 E E E 2000 2000 2000 124A1, A2 124A1 124A1 FM-103B FM-103B FM-103B 6-RC-340-602 E 2000 124A1, A2 FM-103B 6-RC-341-602 E 2000 124Al, A2 FM-103B 6-RC-342-602 E 2000 124A1, A2 FM-103B I Pressurizer Spray 4-RC-314-1502 4-RC-315-1502 2-Cll-3 68-1502 E E E 2771 2771 2771 125Al 125Al 125Al FM-103B FM-103B FM-103B HP Steam to 4-SilP-12 5-601 E 2862 131A1 FM-14A Auxiliary 3-SHP-132-601 E 2862 131A1 FM-14A Feedwater 3-SHP-128-601 E 2862 131A1 FM-14A Pump 3-SHP-131-601 E 2862 131A1 FM-14A 3-SilP-157-601 E 2862 131A1 FM-14A 4-SHP-126-601 E 2864 131B1 FM-14A I 3-SHP-129-601 4-SHP-127-601 3-Slip-130-601 E E E 2864 2869 2869 131B1 131C1 131C1 FM-14A FM-14A FM-14A 3-SHP-135-601 c. 2869 131C1 FM-14A Containment 10-CS-104-153 S&W 2521 123Al FM-101A and Recir- 8-CS-123-153 S&W 2521 123Al FM-101A culation Spray 10-CS-103-153 S&W 2533 123Al FM-101A 8-CS-122-153 S&W 2533 123Al FM-101A 10-CS-103-153 S&W 2547 123Cl FM-101A I 8-CS-133-153 10-CS-104-153 8-CS-134-153 S&W S&W S&W 2547 2549 2549 123C1 123C2 123C2 FM-101A FM-101A FM-101A 10-RS-112-153 E 2546 123D1 FM-101A 8-RS-123-153 E 2546 123D1 FM-101A 10-RS-104-153 E 2541 123D2 FM-101A 8-RS-121-153 E 2541 123D2 FM-101A 10-RS-103-153 E 2542 123D3 FM-101A 8-RS-120-153 E 2542 123D3 FM-101A 10-RS-111-153 E 2543 123D4 FM-101A 8-RS-122-153 E 2543 123D4 FM-101A I A-5
SUKRY POWER STATION - UN." 2 Responsi- . low bilities Problem MKS Diagram Systen Line No. for Analysis No. No. No. Containment 10-RS-112-153 E 2560 123El FM-101A and Recir- 10-RS-104-153 E 2561 123E2 FM-101A culation Spray 10-RS-110-153 E 2544 123G1 FM-101A I (Cont'd) 10-RS-109-153 10-RS-103-153 E E 2533 2548 2545 123G2 123H1 123H2 FM-101A FM-101A FM-101A 10-RS-111-153 E 8-CS-134-153 E 2744 z l'3J1 FM-101A 8-CS-133-153 E 2745 123K1 FM-101A 12-CS-102-153 E 2753 123L1 FM-101A FM-101A I 2754 12-CS-101-153 E 123M1 10-RS-109-153 E 2751 123N1 FM-101A 4-RS-114-153 E 2751 123N1 FM-101A 10-RS-110-153 E 2752 123N2 FM-101A 4-RS-ll5-153 E 2752 123N2 FM-101A I 8-CS-133-153 8-CS-134-153 4-CS-135-153 E E E 2755 2755 2755 123P1 123P1 123P1 FM-101A FM-101A FM-101A 4-CS-136-153 E 2755 123P1 FM-101A I 4-CS-105-152 1/2-CS-108-153 E E 2755 2755 2755 123P1 123P1 123P1 FM-101A FM-101A FM-101A 4-CS-106-152 E
'
10-RS-101-153 E 2756 123Q1 FM-101A 10-RS-102-153 E 2757 123Q2 FM-101A Component 18-CC-15-121 E 2604 112AA1 FM-22A Cooling 18-CC-9-121 E 2605 112AB1 FM-22A 18-CC-7-121 E 2601 112S1 FM-22A I 18-CC-14-121 E 2603 2650 ll2S2 137A FM-22A FM-102A Containment 8-CV-108-151 S&W Vacuum I Note: E = EBASCO S&W = Stone & Webster A-6
i
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_ w
._
_ SULTRY POWER STATION - U:1I r 2 _
-
a APPENDIX B FLOW DIAGRAMS - IDENTIFICATION OF PROBLEMS REANALYZED _
- ._ -
B- 1
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_ _ . . . .
_ . . _ . . _ _ _ _ _ SURRY POWER STATION - UNIT 2 APPENDIX B FLOW DIAGRAMS - IDENTIFICATION OF PROBLEMS REANALYZED Title Drawing No. Main Steam 1154'a-FM-14A Feedwater ll548-FM-18A Cross-Connects for Auxiliary Feed ll448-FM-18B Circulating and Service Water 11548-FM-21A Camponent Cooling Il548-FM-22A Containment and Recirculating Spray ll548-FM-101A Containment Vacuum and Leakage Monitor ll548-FM-102A Reactor Coolant Sheet 1 Il548-FM-103A Reactor Coolant Sheet 2 Il548-FM-103B Residual lleat Removal ll548-FM-104A Chemical and Volume Control Sheet 2 Il548-FM-105B Safety Injection Sheet 1 Il548-FM-106A Safety injection Sheet 2 Il548-FM-106B Refueling Water Storage Tank Crosstie ll448-FM-106C B- 2 _ _ _ _
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.rv ~ a.. a .....,. .. . . , ;_ , D i e ..o.,. .... . ,. t.,o . ., }\ s 1aa 1 - .u a a M Ks. I'D G 2 . _ . . . . - i ? _ e 3 FLOW B VALVE NUMBERS R.W S.T. C R O S S TIE guaRT P0wt e ST&fl0N V. E. P C O. , . .a , . ...,........r.. + " * .., a 3 114 48-FM-106C ' I . _ . . _ _ . _ - - _ _ _ _ __ SURRY POWER STATION - UNIT 2 _ _. APPENDIX C RESPONSE TO IE BULLETIN 79-04 _ _- C-1 _ _ _ _ _ _ . . , _ . _ _ _ _ _ - , _ _ . SURRY POWER STATION - UNIT 2 APPENDIX C RESPONSE TO IE BULLETIN 79-04 Velan swing check valves, sized 3 and 6 inches, are installed in the following seismic Category I piping systems: a) Chemical and volume control system b) Safety injection systems A detailed li st ing by line number is contained in the following table. ._ L.nes with 6 inch check valves were originally seismically analyzed by - couputer program or hand calculations. The re-evaluation of these systems __ ustng the correct valve weight is currently being done ut.d e r the NUPIPE pr ogram. The results have shown that the pipe stress is within the allow-able for all lines. Lines with 3 inch check valves were analyzed originally by hand calcula-tions. % c:!imated weight, overly conservative, was used instead of actual valve weights. The incorrect valve weight has no ef fect on these calculations and re-evaluation is not required, however, these valves and the related pipe lines are included in the scope of IE Bulletin 79-14. .. .. _. C-2 - - - . . . . - - - __ SURRY POWER STATION - UNIT 2 _ LISTING OF VELAN SWING CHECK VALVES COVERED BY IE BULLETIN NO. 79-04 SAFETY INJECTION SYSTEMS - UNIT 2 6 Inch 2-SI-79 6-RC-317-1502 2-SI-82 6-RC-319-1502 2- S I-8 5 6-RC-320-1502 2-SI-88 6-PC-318-1502 2-SI-91 6-RC-316-1502 2-SI-94 6-RC-321-1502 _ 2-SI-228 6-SI-249-1502 2-SI-229 6-SI-249-15G2 2- S I-2 38 6-SI-248-1502 2-SI-239 o-SI-249-1502 2- S I-240 6-SI-250-1502 -- 2-SI-241 6-SI-345-1562 2-S I-24 2 6-SI-344-1502 2-SI-243 6-SI-353-1502 - 3 Inch 2-SI-224 3-31-346-1503 2-SI-225 3-SI-270-1503 3-SI-347-1503 - 2-SI-226 2-SI-227 3-SI-272-1503 CHEMICAL AND VOLUME CONTROL SYSTEM - UNIT 2 3 Inch 2-CH-196 3-CH-500-1502 2-C11-2 58 3-CH-381-1503 2-CH-267 3-CH-302-1503 2-Cll-2 76 3-CH-303-1503 2-CH-309 3-CH-3 79- 1503 2-CH-312 - 3-CH-301-1502 . __ C- 3 - - - - - . . . . . . _ _ . _ . . - __ SURRY POWER STATION - UNIT 2 APPENDIX D CORRESPONDENCE WITil Tile NRC D- 1 - - . _ . _ . ___ __ ~ SURRY POWER STATION - UNIT 2 APPENDIX D ._ CORRESPONDENCE WITil NRC The following is a listing of correapondence with the NRC related to the reanalysis effort. Item No. Date Signature Addressee Letter No./ Subject NRC TO VEPCO 1 3/13/79 Denton Proffitt Show Cause Order 2 4/2/79 Stello Proffitt Addendum to Show Cause Order 3 4/13/79 Stello Proffitt Use of Soil Structure Interaction Techniques .. 4 5/18/79 Stello Proffitt Re que st for Further SSI Information 5 5/25/79 Eisenhut Proffitt Factor Adjustment to SSI Calculated Stresses 6 7/18/79 0'Reilly Proffitt Information Pertaining to IE Bulletin No. 79-14, Revision 1 7 8/15/74 0'Reilly Proffitt Letter of Guidance on IE Bulletin No. 79-14 8 8/27/79 Denton Proffitt Lifting of Suspension Required by the Order to Show Cause 9 10/5/79 O'keilly Proffitt Confirmation of Concur-rence 10 10/23/79 Murphy Proffitt Refers to NRC Inspection of Sept. 10-13 and Sept. 19-21, 1979 11 10/24/79 Murphy Proffitt Re fe r s to NRC Inspection of Sept. 13-14, 1979 12 10/25/79 Murphy Proffitt Refers to NRC Inspection of Sept. 26-28, 1979 13 11/15/79 Eisenhut Proffitt Refers to Soil Structure Interaction D- 2 rw m- SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITil NRC Item No. Date Signature Addressee Letter No./ Subject VEPCO TO NBC 14 3/30/79 Spencer Denton/ 198/ Initial Response to Stello Show Cause Order 15 4/19/79 Stallings O'Reilly 270/LER 79-010/013L-0 16 4/23/79 Spencer O'Reilly 289/ Response to IE Bulletin No. 79-07 17 4/24/79 Spencer O'Reilly 238/ Response to IE Bulletin No. 79-07 I 18 4/27/79 Spencer enton/ Stello 311/ Transmittal to Two Sample Problems to EG6G 5/2/79 Observations on I 19 Stallings Denton Reanalysis Effort 20 5/2/79 Spencer Stello 260/ Submittal of SSI Information 21 5/22/79 Ragone llend r i e Comments on Moratorium / I 22 5/24/79 Spencer St e llo Surry Reanalysis Er Response to NRC Letter of 4/2/79 23 5/24/79 Spencer Stello Response to NRC Letter of 5/18/79 24 6/5/79 Spencer Denton Submittal of Report on Reanalysis 25 6/8/79 Spencer Denton Additional Information, Report on Reanalysis of Piping I 26 6/8/79 Spencer Stello Soil Structure Interac-tion Report 27 6/12/79 Spencer Denton Modification Informa-tion, Reanalysis of Piping Systems I I I e. , SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITH NRC Item No. Date Signature Addressee Letter No./ Subject 28 6/15/79 Spencer Denton Schedule and Support Information 29 6/19/79 3 pencer Denton Support Modifications 30 6/25/79 Spencer Denton Support Information, Reanalysis of Piping I Systems 31 8/1/79 Spencer Denton Submittal of Revised Report on Analysis 32 8/21/79 Spencer Denton Analysis Completion of I Designated Supports - Outside Containment 33 10/4/79 Spencer O'Reilly Response to NRC Letter I of 7/2/79 34 10/3/79 Proffitt Denton Seismic Analysis of Piping Systems 35 10/4/79 Spencer O'Reilly Response to IE Letter Dated 9/7/79 36 10/15/79 Spencer O'Reilly Extension of IE Bulletin 79-14 Deadline I 37 11/28/79 Spencer Denton Seismic Analysis of Piping Systems 38 12/7/79 Spencer O'Reilly Response to NRC Letter of 11/8/79 39 12/13/79 Spencer Denton Show Cause Order Reanalysis I 40 12/21/79 Spencer O'Reilly Show Cause 60 Days Analysis Completion I 41 3/22/79 Kennedy S&W to NRC Denton Transmittal of S&W Computer Programs 42 3/30/79 Jacobs Herring Submittal of Computer Outputs I "-' SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITH NRC Item No. Date Signature Addressee Letter No./ Subject I 43 4/3/79 Jacobs Bezler Submittal of Benchmark Problem to Brookhaven National Laboratory 44 4/6/79 Kennedy Denton Transmittal of S&W Computer Programs 45 4/6/79 Jacobs Stello Plan for Verification of Dynamic Analysis Codes 46 4/11/79 Jacobs Bezler Submittal of Computer Outputs 47 4/13/79 Jacobs Stello Update and Status of Verification Plan for Dynamic Analysis Codes 48 4/18/79 Jacobs Hartman Submittal of Computer Outputs 49 4/27/79 Jacobs Bezler Submittal of Benchmark Problems 50 4/27/79 Jacobs Stello Status of Verification Plan for Dynamic Analysis Codes 51 5/8/79 Rossier Neighbors Draft Outline of SSI-ARS Report 52 5/9/79 Kennedy Stello Reference SHOCK 0 Program 53 5/11/79 Kennedy Stello Reference SHOCK 0 Program I 54 5/14/79 Kennedy Denton Proprietary Computer Codes I 55 6/4/79 Jacobs Bezler Submittal of Benchmark Problems 56 6/12/79 Jacobs Bezler Submittal of Benchmark Problems I I e. SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITH NRC No. Date Signature Addressee Letter No./ Subject 57 9/6/79 .len . Stello Response to NRC Letter of 8/10/79 Ebasco to NRC 58 9/7/79 Nelson Hartzman Benchmark Problem VEP/NRC/001 59 1/3/90 Nelson Hartzman Benchmark Problem VEP/NRC/002 I I I I D-6}}