ML18139A144
| ML18139A144 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/11/1980 |
| From: | Spencer W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18139A145 | List: |
| References | |
| NUDOCS 8004140219 | |
| Download: ML18139A144 (84) | |
Text
{{#Wiki_filter:, VIRGINIA ELEC:I'RIC .!\.ND POWER COMPANY RICHMOND,VIRGINIA 23~61 e April 11, 1980 Mr. Harold R. Denton, Director Serial No. l38B Office of Nuclear Reactor Regulation PSE&C/GLS:mac:wang U.S. Nuclear Regulatory Commission Washington, DC 20555 Docket No. 50-281 License No. DPR-37
Dear Mr. Denton:
SHOW CAUSE ORDER REANALYSIS REPORT REVISION NO. 1 SURRY POWER STATION UNIT 2 In the letter of February 22, 1980 (Serial No. 138), Vepco requested start-up of Surry Power Station Unit 2 based on the 11 Report on the Reanalysis of Safety Related Piping Systems, Surry Power Station, Unit 211 of the same date. The report reflected the results of the pipe stress and pipe support analyses subject to final verification and modification installation. The purpose of this submittal is to update the original report to reflect revisions necessitated during modification installation and to make minor typographical corrections to the text to enhance clarity and consistency. The subject changes, which are noted in the margins, in no way alter our original conclusion that the analytical work completed and the modifications installed at the time of start-up provides a high degree of confidence that the integrity of safety systems for Unit 2 can be assured during the DBE or OBE events. This revised report also incorporates our recent commitment to the NRC Staff (Vepco letter of March 21, 1980, Serial No. 138A) to complete the installation of all modifications associated with the Order to Show Cause prior to start-up of the unit. The additional commitments to complete certain portions of the work associated with I.E. Bulletins 79-02 and 79-14 are firm as outlined in the February 22 letter. If you have any questions with regard to this .submittal, please contact us. W. C./ pencer Vice President - P6 er Station Engineering Ao7.:> er and Construction Services s 1/lf o Attachment A~ry. t:1,t ~ cc: Mr. Victor Stello, Director H. 0&/To;y I Office of Inspection & Enforcement Mr. James P. 0 1 Reilly, Director Office of Inspection & Enforcement, Region II 80 041402/. C/
I ~. . n HJ.tu urnioc"ET e,l,iEblh RE. S?iULflTnij'J a\ .fill K:fi1T}\\Ja I . REPORT ON THE I I REANALYSIS OF I SAFETY-RELATED I PIPING SYSTEMS I I SURRY POWER STATION-UNIT 2 I I VIRGINIA ELECTRIC I AND POWER COMPANY I I REVISION 1 I I I EBASCO SERVICES INCORPORATED--- JER1cHo, NEW YORK I Docket#, '>.50- 2-8 I Control # s* ,:,04- , 'I- o :z I 'I I ..REGULATOR'{ DOCKET Fu.LE COPl Date !_ /, I /80 of Documeiif: ll!§§U~fiQ3X P~:cgr fU.~ ' I . , 80 04140 2..2'-f
I VIRGINIA ELEC:rRIC AND POWER COMPANY I RXCHMOND,VI:e:GXNIA 23261 ii April 11, 1980 Mr. Harold R. Denton, Director Serial No. 1388 I Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission PSE&C/GLS:mac:wang
*Washington, DC 20555 Docket No. 50-281 I
Dear Mr. Denton:
License No. DPR-37 I SHOW CAUSE ORDER REANALYSIS REPORT REVISION NO. 1 SURRY POWER STATION UNIT 2 I In the letter of February 22, 1980 (Serial No. 138), Vepco requested start-up of Surry Power Station Unit 2 based on the "Report on the Reanalysis I of Safety Related Piping Systems, Surry Power Station, Unit 211 of the same date. The report reflected the results of the pipe stress and pipe support analyses subject to final verification and modification installation. I The purpose of this submittal is to update the original report to reflect revisions necessitated during modification installation and to make minor typographical corrections to the text to enhance clarity and consistency. The I subject changes, which are noted in the margins, in no way alter our original conclusion that the analytical work completed and the modifications installed at the time of start-up provides a high degree of confidence that the integrity I of safety systems for Unit 2 can be assured during the DBE or OBE events. This revised report also incorporates our recent commitment to the NRC I Staff (Vepco letter of March 21, 1980, Serial No. 138A) to complete the installation of all modifications associated with the Order to Show Cause prior to start-up of the unit. The additional commitm~nts to complete certain portions of the work associated with I.E. Bulletins 79-02 and 79-14 are firm as I outlined in the February 22 letter. If you have any questions with regard to this submittal, please contact us. I Very t~rly.*ours,
~
I . '\;~(!,(.~ W. C. pencer Vice President - Po~er Station Engineering I and Construction Services Attachment I cc: Mr. Victor Stello, Director Office of Inspection & Enforcement I Mr. James P. 0 1 Reilly, Director Office of Inspection & Enforcement, Region II I
I I I* A. Helm Mr. D. F. Cochran be: Mr. J. H. Ferguson Mr. G. Mr. Sam C. Brown, Jr. Mr. A. L. Parrish, III Mr. G. L. Strickler I Mr. Mr. W. C. Spencer C. M. Sta 11 i ngs Mr. Mr. R. F. H. Wood a11 , II I M. Alligood, Jr. Mr. Mr. M. w. Maupin H. w. Nelson - Ebasco Mr. E. A. Baum Mr. R. M. Berryman Mr. J. M. Daly I Mr. Mr. J. w. Waddil 1 D. W. Speidell, Jr. Mr. Mr. C. M. Robinson, Jr.
- w. T. Davidson - Surry Mr.
Mr. R. J. K. MacManus L. Perkins A. Peebles - Surry Mr. W. C. Daley Mr. J. L. Wilson - Surry Mr. T.
- s. C. Rossier - S&W I Mr.
Mr. B. R. Sylvia J. C. Harris, Jr. Mr. B. R. Crowe - S&W Mr. I I I I I I I I I I I I I
I I, .*.. I REPORT ON THE 1* .I REANALYSIS OF I . SAFETY-RELATED I* PIPING SYSTEMS I I* SURRY POWER STATION-UNIT 2 I I VIRGINIA ELECTRIC I: . AND POWER COMPANY . II I* REVISION 1 .** I I EBASCO SERVICES INCORPORATED--- . - - ~ M i d.. JERICHO, NEW YORK I I
ii SURRY POWER STATION - UNIT 2 I 1, I I I I REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS SURRY POWER STATION - UNIT 2 I VIRGINIA ELECTRIC AND POWER COMPANY FEBRUARY 22, 1980 I REVISION 1 I' APRIL 11, 1980 I I I I I,, I EBASCO SERVICES INCORPORATED I JERICHO, NEW YORK I
I SURRY POWER STATION - UNIT 2 I TABLE OF CONTENTS I Section 1.0 Title
SUMMARY
AND CONCLUSIONS .................*......* 1-1 I 2.0 3.0 4.0 SCOPE OF REANALYSIS ...*......................... PIPE STRESS RESULTS .......................*.*..* PIPE SUPPORT RESULTS ..*...........*......*...... 2-1 3-1 4-1 5.0 SCHEDULE FOR COMPLETION ........................ . 5-1 I 6.0 7.0 HIGH ENERGY LINE BREAKS ........................ . CONSERVATISMS .................................. . 6-1 7-1 I 7.1 7.2 7.3 Field Verification of As-Built Conditions .... . Quality Assurance and Engineering Assurance .. . Use of Amplified Response Spectra ............ . 7-1 7-1 7-1 7.4 Conservatisms Applied to Inertial Stress ..... . 7-2 I 8.0
- 9 .0 SYSTEM OPERABILITY EVALUATION .................. .
BRANCH LINE
SUMMARY
8-1 9-1
- 1 10.0 RESPONSE TO THE NUCLEAR REGULATORY COMMISSION'S CONCERNS .......................... . 10-1 10.1 Support Stiffness ............................ . 10-1 I 10.2*
10.3 NUPIPE Computer Code ......................... .
.* Problem 2538 - Support H-15 .................. .
10-1 10-1 10.4 Benchmark Problems ........................... . 10-2 I Appendix 1* A B Systems Affected .................................. . Flow Diagrams - Identification of Problems Analyzed B-1 A-1 C Response to IE Bulletin 79-04................... C-1 I D Correspondence with. the NRG..................... D-1 I 1, I I II I 1- i
I SURRY POWER STATION - UNIT 2 I SECTION 1 I
SUMMARY
AND CONCLUSIONS In response to the Nuclear Regulatory Commission's Order to Show Cause, I 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* SHOCK 2 computer program. The SHOCK 2 program, which used an earlier load combination methodology, is no longer considered ac-I ceptable by the NRC, This report discusses the details of the analysis work and results of the I pipe and support analyses within the scope of the reanalysis for Surry Unit 2. Further,. this reanalysis 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 I (Vepco Serial No. 453A) and on January 15, 1980 (Vepco Serial No. 048). This report summarizes the total reanalysis effort for all aspects of the March 13, 1979 Order to Show Cause for Surry Power Station Unit 2. All piping systems affected by the Order to Show Cause, both inside and outside the containment, have been reanalyzed using the NUPIPE program, which is acceptable to the NRC. Table 3-3 (Pipe Stress Hardware Modi-I 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 I 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. f1 I All pipe supports both inside and outside containment affected by the Order to Show Cause have been evaluated for the revised support 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 gen-I erator replacement outage. Table 4-2 (Pipe Support Hardware Modification Summary) reports all the modifications resulting from the support re-analysis. As was the case in the piping system reanalysis, most of the I modifications are the result of differences between the original design ,. conditions and the actual field as-built condition. During the reanalysis of Surry Unit 2, 79 stress modifications (22 due to pipe stress, 57 due to nozzle overload) and 258 pipe support modifications were identified; while 63 pipe stress and 66 pipe support modifications 1 were identified on Surry Unit 1, The differences in the number of modif-I ications is not considered significant, due to the conduct of the re-analys*is applied to Surry Unit 2. Modifications on Surry Unit 1 were 1-1 I
I I SURRY POWER STATION - UNIT 2 identified after many analytical iterations; whereas, on Surry Unit 2 modifications were designed based on fewer iterations. The conduct of the I reanalysis in this manner served to identify modifications faster so that systems could be upgraded more quickly in order not to substantially inter-fere with the completion of the Steam Generator Replacement Project. In I addition, the Surry Unit 2 reanalysis included the QBE condition. Further, all pipe supports were as-built in the field and QC verified prior to re-analysis. Lastly, to limit the interface problems between the Show Cause 1* scope and other piping, supports were added to facilitate the NUPIPE re-analysis. I I I I I I I I 1-2
I SURRY POWER STATION - UNIT 2 SECTION 2 I SCOPE OF REANALYSIS As described 1.n the NRC Order to Show Cause, March 13, 1979, some p1.p1.ng systems in the Surry Power Station, Unit 2 were dynamically analyzed with a SHOCK 2 computer program that is not currently acceptable to the NRC. All systems or portions of . systems that were analyzed by the SHOCK 2 computer program have been identified in Appendix A. These systems were reanalyzed by Stone & Webster Engineering Corporation (Stone * & Webster) and Ebasco Services Incorporated (EBASCO) using a NUPIPE com-puter code. Responsibility for the reanalysis is also identified 1.n Appendix A by system and problem number. I The results of the reanalysis are compared with code allowable stresses, allowable loads for nozzles and penetrations, and are in the evaluation of pipe supports. pipe used I I
- I I
I I I I I I I 2-1
I I SURRY POWER STATION - UNIT 2 SECTION 3 I PIPE STRESS RESULTS A total of 62 pipe stress problems were originally analyzed by the PSTRESS/ I SHOCK 2 computer I 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 I (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 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 stress 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 technique for inter-modal combination. I Piping is analyzed in most cases utilizing amplified response spectra (ARS) that are developed using soil structure interaction techniques (SSI-ARS). I The resultant stresses and loads are used to evaluate piping, supports, nozzles, and penetrations. In accordance with the NRC letters of May 25, 1979 and November 15, 1979 to Virginia Electric and Power Company (VEPCO), I 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 I 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 {sometrics (MSK' s). 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 3-1 reports DBE I results, stress analysis is performed for OBE also and modifications de-signed wherever necessary. 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-I 'I 3-1
I SURRY POWER STATION - UNIT 2 I gram using different mass models and in most cases different ARS's than the original calculations. More importantly, the reanalyses were based on I 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 I necessarily represent the same physical conditions.
Table 3-2, Nozzle and Penetration Summary, summarizes the nozzles and pene-trations evaluated under the reanalysis program. For all the problems in I 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 Hardware Modification Summary, lists the hardware modifications necessary to bring the pipe stress analysis to within code allowables. Of the 62 problems reanalyzed, hardware modifications were made to 17 problems due to pipe stress. These modifications consisted of 22 added, modified, or deleted supports. The modifications include those necessary to the flexibility analysis of the branch lines. A branch line I (Problem No. 2508B) was rerouted as a result of thermal reanalysis, not as a result of seismic reanalysis. I 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 I added, modified, or deleted supports. 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, Pipe Support Hardware Modification Summary. Final verification of piping and support stresses and Engineering Assurance review has yet to be completed for a few problems. It is ex-I pected, however, that the number and type of modifications due to the stress and support analysis are correct and final. I I I 3-2
SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet l of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name Line Size and Pi12e Stress ( 12si) Reanalysis MKS NPS Original Original Problem Number + Res12onsibilit:t: Number (Inches) New New Total Seismic Total Seismic Allowable Low Head Safety Injection 2555 E 122Dl 10,12 12043 NA 7974 2449 30690 2709 E 12211 12 NA NA 19173 11427 33750 2537/2540/2540B E 122Al, 4,6, 12350 NA 2739 883 33750 117Bl 10,12 2539 E 122Jl 6 30368 NA 14771 7330 32985 122Kl 11 2727 S&W 127Cl 6 21179 NA 24352 17453 33750 12JC2 8,10 2681 E I27Kl 8 1677 307 1220 185 28485 2682 E 127K2 8 i677 307 1174 164 28485 2695 E 127Dl 8 21179 NA 2094 1103 28485 2697 E 127D2 8 21179 NA 1981 1022 28485 High Head Safety Injection 2689 E 127Fl 10 24649 NA 11773 9571 33750 2735 E 127Gl 3,4,6, NA NA 26660 17772 33750 127G2 8,10 Containment and Recirculation S12rai 2521 S&W 123Al. 8, 10 14904 NA 7790 4276 33561 2523 S&W 123A2 8,10 14904 NA 7977 6013 33561 2547 S&W 123Cl 8,10 12713 NA 23532 19 739 33561 2546 E 123Dl 8,io 3528 1576 8892 7328 28800 2541 E 123D2 8,10 3528 1576 18338 16636 28800 2542 E 123D3 8,10 3528 1576 18931 17252 28800
-: - - .. .. - - - '*- - - - ... .. .. .. - - - SURRY POWER STATION - UNIT 2 I
TABLE 3-1 Sheet 2 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name Line Size Pi:ee Stress (:esi) and Reanalysis MKS NPS Original. Original New New Problem Number Res:eonsibiliti Number (Inches) Total Seismic Total Seismic Allowable Containment and Re-circulation s:erai (Cont'd) 2543 E l23D4 8,10 3528 1576 8498 6988 29970 2560 E 123El 10 7334 NA 12775 10995 29970 2561 E 123E2 10 7334 NA 6587 3576 29970 2544 E 123Gl 10 11605 7922 2912 1181 28485 2533 E 123G2 10 11605 7922 5874 3813 28485 2548 E 123Hl 10 15785 11241 3904 2437 29970 2545 E 123H2 10 15785 11241 2397 676 29970 2744 E 123Jl 8 7966 5118 16143 15187 35820 2745 E 123Kl 8 24843 22577 15621 12559 33750 2753 E 123Ll 12 6136 2818 1344 394 33750 2754 E l23Ml 12 5649 NA 1999 949 33750 2751 E 123Nl 10 6010 NA 21234 13842 28485 2752 E. 123N2 10 6010 NA 18613 13934 28485 2549 S&W 123C2 8 11955 10125 10081 8397 33561 2755 E 123Pl 4,8 10369 6324 14311 7340 33750 2756 E 123Ql 10 NA NA 5705 2686 28485 2757 E 123Q2 10 5810 NA 3847 2381 28485* Main Steam 2577 S&W 100Dl 30 13824 NA 10763 2883 33750 2588 S&W 101Dl 30 18635 NA 12513 3041 33750 2579 S&W 102D2 30 13031 NA 11434 4120 33750 2346* S&W 103Al 30 19970 NA 32568 25477 33750 103A2 L_ _ _ _ -
SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 3 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name. Line Size Pipe Stress (psi) and Reanalysis MKS- NPS Original Original New New Responsibility Number (Inches) Total Seismic: Total Seismic: Allowable Problem Number Feedwater S&W lOOGl 14 14499 NA 13681 9360 27000 2569 S&W 101Gl 14 16025. NA 12970 8376 27000 2573 S&W 102Gl 14 17927 NA 14230 8443 27000 2571 Auxiliary Feedwater E 118Al 3,6 8568 2407 20963 17736 27000 2473 118A2 118Gl 4,6 21230 NA 12988 9188 27000 2683 E 118G2 Pressurizer Spray E 125Al 4 18560
- NA 8013 3088 30690 2771 Pressurizer Safety and Relief E 124Al 3,4 9093 NA 8824 5421 30636 2000 124A2 6, 12.
Residual Heat Removal 2540/2540B E Listed Under Low Head Safety Injection System E ll 7Al 10,12,14 NA NA 13112 8461 24570 2508A/2508B E 117Cl 6 NA NA 12008 8824 29970 2554 Service Water E 119Al 24 NA NA 6529 6212 21600 2465 E 119A2 24 NA NA 6561 6214 21600 2467
SURRY POWER STATION - UNIT. 2 TABLE 3-1 Sheet 4 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
System Name Line Size PiEe Stress (Esi) and Reanalysis MKS NPS Original Original New New Problem Number ResEonsibility Number (Inches) Total Seismic Total Seismic Allowable Service Water (Cont'd) 2469 E 119A3 24 NA NA 14687 13730 21600 2471 E 119A4 24 NA NA 12459 11:614 21600 ComEonent Cooling 2601/2603 E 112Sl 18 9696 NA 7043 5246 21600 112S2 2604/2605 E 112AA1 18 9696 NA 7074 5204 21600 112AB1 Containment Vacuum 2650 S&W 137Al 8 25,750 NA 13659 13037 21600 HP Steam to Auxiliary Feedwater Pum:e 2869/2862/2864 E 131Al 3,4. 22609 NA 24229 19559 27000 131Bl 131Cl
SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 5 of 5 PIPE STRESS RE-EVALUATION
SUMMARY
Legend: E = EBASCO S&W = Stone & Webster* NA = Not Available Allowable Stress = 1.8 sh New Total Stress (for SSI/ARS) SLP + SDW + l.S SDBEI + SDBEA New Seismic (for SSI/ARS) l.S SDBEI + SDBEA New Total Stress (original ARS) 1 SLP + SDW + SDBEI + SDBEA = Original Total Stress New Seismic (original ARS) SDBEI + SDBEA = Original Seismic Stress 1 Where SLP Longitudinal P~essure Stress SDW Dead Load Stress SDBEI Seismic Inertial Stress, Design Basis Earthquake SDBEA Seismic Stress due to Anchor Movements, Design Basis Earthquake sh = Allowable stress at maximum (hot) temperature Note: The original total and original seismic stresses shown in Table 3-1 were computed using SHOCK 2 for the original design conditions. The new total and new seismic stresses were computed by the NUPIPE program using different 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, differ 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: 2869/2862/2864 are counted as three problems. Using this method of counting the total number of pipe stress problems equal 62.
I I SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 1 of 4 I NOZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems I System and Responsi-bility For Total No. o~ Nozzles/ No. Acceptable (Evaluation Nozzle Modification Vendor Confirmation Being Problem No. Analysis Penetrations Complete) Required Obtained I Low Head Safety I Injection 2555 E 1/0 1 0 1 I 2709 E 1/0 1 0 0 2537/2540 E 1/0 1 0 1 I 2539 E 0/0 NA NA NA I 2727 2681 S&W E 2/0 0/0 2 NA 0 NA 2 NA I 2682 E 0/0 NA NA NA 2695 E 0/0 NA NA NA I 2697 E 0/0 NA NA NA I High Head Safety Injection I 2689 E 0/0 NA NA NA 2735 E 3/0 3 0 3 I Containment and Recirculation I Spray 2521 S&W .0/0 NA NA NA I 2523 S&W 0/0 NA NA NA 2547 S&W 0/0 NA NA NA I 2546 E 0/0 NA NA NA I I
I SURRY POWER STATION - UNIT 2 I TABLE 3-7 Sheet 2 of 4 I NOZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems I System and Responsi-bility For Total No. of Nozzles/ No. Acceptable (Evaluation Nozzle
- Modification Vendor Confirmation Being Problem No. Analysis Penetratioqs Compl~te) Required Obtained I Containment and Recirculation I Spray (Cont'd) 2541 E 0/0 NA NA NA I 2542 E 0/0 NA NA NA 2543 E 0/0 NA NA NA I 2560 E 1/0 1 0 0 I 2561 2544 E
E 1/0 1/0 1 1 0 0 0 0 I 2533 2548 E E 1/0 1 0 0 1/0 1 0 0 I 2545 E 1/0 1 0 0 2744 I 2745 E* E 0/0 0/0 NA NA NA NA NA NA I 2753 2754 E E
- 1/0 1/0 1
1 0 0 0 1 I 2751 E 2/0 2 0 0 2752 E 2/0 2 0 0 I 2549 S&W 0/0 NA NA NA I 2755 2756 E E 2/0 2/0 2 2 0 0 2 0 I 2757 E 2/0 2 0 0 I I
I SURRY POWER STATION - UNIT 2 I TABLE 3-2 Sheet 3 of 4 I NOZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems Vendor I System and Responsi-bility For Total No. of Nozzles/ No. Acceptable (Evaluation Nozzle
- Modification Confirmation Being Problem No. Analysis Penetrations Complete) Required Obtained I Main Steam I 2577 2588 S&W S&W 1/1 1/1 1/ 1 1/1 0/0 0/0 0/0 0/0 I 2579 2346 S&W 1/1 1/1 0/0 0/0 S&W 0/0 NA NA NA I Feedwater 2569 S&W 1/1 I 2573 S&W 1/1 1/ 1 1/1 0/0 0/0 0/0 0/0 I 2571 Auxiliary Feedwater S&W 1/1 1/1 0/0 0/0 I 2473 E 0/0 NA NA NA 2683 E 3/0 3 0 3 I Pressurizer Spray I 2771 E 1/0 1 0 1 Pressurizer I Safety and Relief 2000 E 5/0 5 0 1 I Residual Heat Removal I 2540 E (Listed under Low Head Safety Injection System)
I I I
I I SURRY POWER STATION - UNIT 2 TABLE 3-2 .Sheet 4 of 4 I NOZZLE AND PENETRATION
SUMMARY
SHOCK 2 Problems I System and Respon1;i-bility For Total No. of Nozzles/ . No. Acceptable (Evaluation Nozzle Modification Vendor Confirmation Being Problem No. Analysis Penetrations Complete) Required Obtained I Residual Heat Removal (Cont'd) I 2540B E 0/0 NA NA NA I 2508A/2508B 2554 E E 8/0 0/0 8 NA 0 NA 8 NA I Service Water 2465 E 1/0 1 0 0 I 2467 E 1/0 1 0 0 2469 E I 2471 E 1/0 1/0 1 1 0 0 0 0 I Component Cooling 2601/2603 E 2/0 2 0 1 I 2604/2605 E 2/0 2 0 1 Containment I Vacuum
~...,..
2650 S&W 0 NA NA NA I HP Steam to Auxiliary Feedwater Pump I 2862/2864/2869 E 1/0 1 0 0 I NOTES: NA = Not Applicable I E = EBASCO S&W = Stone & Webster I I
SURRY POWER STATION - UNIT 2 TABLE 3-3 Sheet 1 of 2 PIPE STRESS HARDWARE MODIFfCATION
SUMMARY
System Name Reanalysis MKS Attributed and Problem No. Responsibility No. Overstressed Condition To: Resolution No. of Modifications Low Head Safety Injection 2709 E I22Ll *Seismic overstress Seismic Spring hanger replaced 1 Reanalysis by rigid restraint. 2537/2540 E 122Al Thermal overstress As-built Removed a restraint, 2 117:Bl anchor replaced by restraints and a snubber. 2539 E I22Jl Thermal overstress As-built Removed a restraint l 122Kl (Branch Line) Containment and Recirculation Spray 2549 S&W I23C2 Pipe contacts crane Seismic Lateral support added. l wall *during. *seismic Reanalysis condition. 2544 E I23Gl Thermal overstress As-built Removed a restraint. 1 2745 E I23Kl Seismic anchor move- As-built Vertical restraints 2 ment overstress replaced by spring hangers at two loca-tions 2752 E I23N2 Thermal overstress As-built Removed a restraint. l (Branch Line)
/
/
Pressur;i;r Spray/ 2771 E 125Al Seismic overstress As-built Two restraints added. 2 Residual Heat Removal /' 2508B E 117Al Thermal overstress As-built Rerouting of 1-1/2 in. l Branch* line pipe 2540 (Listed under Low Head Safety Injection System) I l
SURRY POWER STATION - UNIT 2 TABLE 3-3 Sheet 2 of 2 PIPE STRESS HARDWARE MODIFICATfON
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 117B Thermal and seismic As-built Anchor replaced by 2 overstress vertical restraint, horizontal restraint removed. Component Cooling 2604/ E 112AA1 Seismic overstress Seismic Two restraints added. 2 2605 112AB1 Reanalysis HP Steam to Auxiliary Feedwater Pump 2862/ E 131Al Thermal and seismic As-built/ Two anchors replaced 5 2864/ 131Bl overstress Seismic by restraints, two 2869 131Cl Reanalysis snubbers and a spring added. Feedwater 2569 S&W lOOGl Insufficient branch As-built Remove existing 1 line flexibility U-bolt on 3/4 in. line Notes: E EBASCO S&W Stone & Webster
--- --------------- SURRY POWER STATION - UNIT 2 TABLE .3-4 Sheet 1 of 2 HARDWARE MODIPICATION
SUMMARY
DUE TO NOZZLE AND PENETRATION OVERLOADING System Name Reanalysis Attributed and Problem No. Responsibility Equipment No. To: Resolution No. of Modifications Low Head Safety Injection 2555 E 2-SI-TK-lB As-built/ One restraint 2 1 Seismic added*, One spring hanger Reanalysis replaced by a two direction restraint High Head Safety Injection 2735 E 2-CH-P-lA Seismic Ten restraints added, 13 2-CH'-P-lB Reanalysis one ve~tical restraint 2-CH-P-lC replaced by spring hanger, two anchors added Containment and Recirculation
~
2544 E 2-RS-E-lD As-built One restraint removed 1 2533 E 2-RS-E-lC As-built Two restraints added 2 2753 E 2-CS-P-lB As-built/ One vertical restraint 3 Seismic replaced by spring Reanalysis hanger, two restraints added 2754 E 2-CS-P-lA As-built/ One vertical restraint 2 Seismic replaced by spring Reanalysis one horizontal restraint added. 2751 E 2-RS-P-2A Sei~mic One restraint added 1 Reanalysis
. 2752 E 2-RS-P-2B Seismic One restraint added 1 Reanalysis 2755 E 2:-CS-P-lB As-built/ One restraint added 3 2-CS-P-lA Seismic two vertical restraints Reanalysis removed.
2756 E 2-RS-E-lA As-built One anchor and one 2 2-RS-P-lA restraint removed
SURRY POWER STATION - UNIT 2 TABLE 3-4 Sheet 2 of 2 HARDWARE MODIFICATION
SUMMARY
- DUE TO NOZZLE AND PENETRATION-"*OVERLOADING System Name Reanalysis Attributed and Problem No. Responsibility Equipment No. To Resolution No. of Modifications Containment and Recirculation Spray (Cont'd) 2757 E 2-RS-E-lB As-built One anchor removed 2-RS-P-lB 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 Removal 2508B E 2-RH-P-lA Seismic Six snubbers added, two 10 2-RH-P-lB Reanalysis springs replaced by restraints, one spring hanger added, one vertical restraint added. Service Water 2471 E 2-RS-E-lD As-built One restraint removed l Component Coolin!!; 260 I/ 2603 E 2-RH-E-lB As-built Four vertical restraints 6 Seismic replaced by springs and Reanalysis snubbers, two restraints added. Note: E EBASCO
I SURRY POWER S'rA.TION - UNIT 2 I SECTION 4 I PIPE SUPPORT RESULTS Table 4-1, Pipe Support An~lysis Summary, summarizes the pipe support reanalysis program. Six hundred ninety four (694) supports (467 inside the I ~ontainment, 218 outside the containment) on lines originally analyzed using Shock 2, were rean~lyzed as part of this Show Cause effort. Two hundred fifty eight (258) hardware modifications (175 iqside the containment, 83 1 I outside:the conta:tnment) hav~ been identified. The modifications identified due to i the pipe support reanalysis are l;i.sted in Table 4-2, P:i,pe Support Hardware Modification Summary. I 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 identified, I only 109 were* the result* of seismic reanalys;i.s of the piping systems iden-tified in the
- Show Cause Order, while 149 were the result of differences identified between the as-built cot1ditions and the original design. These I conditions 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 I
- of May 25, 1979, and by a factor of 1. 25 for OBE per the NRC letter of November 15, 1979 *.
I I I I .:.~ I I I I I I
SURRY POWER STATION - U!HT 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 Inject:ion System 2537/2540 E IC 33. 33 17 1
2555 2539 E IC 17 17 9 f E IC 7 7 5 2681 E OC 4 4 3 2682 E OC 4 4 3 2695 E 1 OC 10 HJ 4 2697 E oc 9 9 6 27u9 E IC 9 9 3 2727 S&W OC 17 17 8 I 1 High Head Safety Injection --- -*-* System 261:19 E oc 5 5 4 2735 E OC 52 52 23 I1 Containment and Recirculation Spray 2521 S&W IC 15 15 4 2523 S&W IC 16 16 5 2547 S&W IC 13 13 6 2549 S&W IC 4 4 1 2546 E IC 12 12 6 I1
SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 2 of 4
~.
PIPE SUPPORT ANALYSIS
SUMMARY
System Name Total Modifications and Analysis Number of Evaluation or Additions Problem Number Res12onsibility Location Su1212orts Com12lete Required Containment and Recirculation
~ (Cont'd) 2541 E IC 11 11 6 2542 E IC 11 11 4 2543 E IC 12 12 6 2560 E IC 4 4 1 11 2561 E IC 5 5 3 2544 E IC 6 6 2 11 2533 E IC 5 5 1 2548 E IC 15 15 6 Ji 2545 E IC 17 17 9 2744 E OC 4 4 3
-*-~--
2745 E oc 4 4 2 11 2753 E QC 4 4 1 2754 E oc 3 3 1 27 51 E oc 5 5 l 2752 E oc 4 4 0 27.'.>5 E oc 8 8 4 1
~756 E IC 7 7 2 2757 E IC 9 9 3
SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 3 of 4
~
PIPE SUPPORT ANALYSIS
SUMMARY
System Name Total Modifications and Analysis Number of Evaluation or Additions Problem Number ResEonsibility Location su12Eorts ComElete Required Main Steam 2577 S&W IC 9 9 2 2588 S&W IC 2 2 0 2579 S&W IC 5 5 3 2346 S&W QC 41 41 6 Feedwater 2569 S&W IC 9 9 4 2573 S&W IC 3 3 0 2571 S&W IC 6 6 1 Auxiliarx Feedwater 2473 E IC 34 34 12 1 2683 E QC 22 22 8 Pressurizer SEray
*and Relief 2771 E IC 32 32 7 2000 E IC 29 29 15 11 Residual Heat Removal 2508A/B E IC 45 45 4 2540B E IC 5 5 4 1 2554 E QC l l l
SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 4 of 4 PIPE SUPPORT ANALYSIS
SUMMARY
System Name Total and Modifications Analysis Number of Evaluation or Additions Problem Number Responsibility Location Supports Complete Required Service Water 2465 E IC 2 2 l 2467 IC 2 2 l 2469 E IC 1 1 0 2471 1 E IC 1 l 1 Component Cooling 2601 E IC 16 16 5 2603 E IC 13 13 5 2604 1 E IC i7 17 7 2605.. E IC 17 17 4 Containment Vacuum 2650 S&W oc 3 3 3 1. High Pressure Steam to Aux Feedwater Pump 2862 E oc 6 8 l 11 2864 E oc 3 3 (J 2869 E oc 7 7 1 Notes: E = EBASCO S&W = Stone & Webster IC= Inside Containment OC = Outside Containment
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 1 of lL. PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE AND PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION I I I Low Head Safeti Injection Sistem I 2537/2540 E IC 2537 E IC 2,4 Local pipe wall. stress Seismic Hodify support over allowable Reanalysis 11 6 Support member over allowable As-built Modify support 9 Support does not allow.lateral As-built Hodify support movement /1 2540 E IC 5 Insufficient clearance Seismic llodify support Reanalysis 7,8,9,10,13,26 Support member over allowable As-built Modify support t1 12,28 Pipe clamp over allowable As-built Modify support 11 17,19 U-bolt over allowable As-built Modify support 1 Weld over allowable As-built Add weld 11 8A Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift lo_ad 2555 re; E 8 Support member over allowable As-built Modify support I1 3 Weld over allowable As-built Add weld 4,5 Local pipe wall stress over Seismic Modify support allowable Rea_nalysis 11 9,12 Support member over allowable Seismic Modify support Reanalysis /1 12A Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 13,14 Insufficient lateral clearance As-built Modify support 11 2539 E IC 2 Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 1 Upward 'vertical restraint. Seismic Hodify restraint required Reanalysis for uplift load
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 2 of 12 PIPE SUPPORT HARDWARE MOOIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Low Head .Safety Injection sistem (Cont'd) 2539 (Cont'd) E IC H-1** Support member over allowable As-built Modify support 11 3,4 Support member over allowable As-built Modify support 2709 E IC 7 Support 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 Seismic Modify Support allowable Reanalysis 11 Loads out of range of spring As-built Replace spring. 14 Loads out of spring range Seismic Replace spring Reanalysis 15 Loads out of spring range Seismic Replace spring
-Reanalysis 16 Loads out of spring range Seismic Replace spring Reanalysis 11 18 Loads out of spring range Seismic Replace spring Reanalysis 19 Supports restraint lateral As-built Modify Support movement 11 2695 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 Modify support
- - - - - - - - - - - - - - - - - - .. SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 3 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Low Head Safety Injection System (Cont'd) 2697 E QC H-49 Support member over allowable As-built Modify support C-7 Support not acting As-built Removed support C-17,C-18 Support member over allowable As-built Modify support A-14 Support member over allowable As-built Modify support A-15 Support member over allowable As-built Modify support 2681 E QC 2,4 Support member over allowable As-built Modify support 5 U-bolt over allowable As-built Modify support 2682 E oc 4 Support member over allowable As-built Modify support 2 Support member over allowable As-built Modify support 5 U-bolt over allowable As-built Modify support High Head Safety _Injection System 2689 E oc C-38,C-39 Support member over allowable As-built Modify support C-40,C-41 Support* member*over allowable As-built Modify support 2735 E oc 19,34,42 Support member over allowable As-built Modify support I1 22,37 ,45,28 36,21,23,44 1,3,16,31,39,24 Weld over allowable As-built Add weld 4,6,18,33,41 U-bolt cive:r allowable Seismic Modify support reanalysis 26 Local pipe* *will stress Seismic Modify support over allowable reanalysis I1 Containment and Recirculation Spray 2521 S&W IC 2 U-bolt capacity for side- Seismic Add members to load in insufficient Reanalysis resist side load
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 4 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS MID ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER* MODIFICATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) 2521 (Cont'd) S&W IC 3 Frame overstressed with Seismic Modify existing new loads out-of springs Reanalysis frame and replace range springs 4 U-strap has insufficient Seismic Replace existing capacity Reanalysis strap with new framing 5 Local stress Seismic Eliminate anchor Reanalysis and. add" vert/lat restraint 2523 S&W IC l U-bolt capacity for side- Seismic Add members to load is insufficient Reanalysis resist sideload 2 Frame overstressed Seismic Replace existing Reanalysis frame 3 Capacity of springs in- Seismic Replace springs sufficient Reanalysis 4 U-strap has insufficient Seismic Replace existing capacity Reanalysis strap with new framing 5 Local stress Seismic Eliminate anchor Reanalysis and add vert/lat restraint 2547 S&W IC 2 Lateral load fails U-bolt As-built Add lateral restraint 4 Rod hanger cannot resist Seismic Replace with upward load Reanalysis sway strut 6 Insufficient clearance As-built Remove lateral for thermal movement stop 8 Insufficient latera-1 As-built Remove lateral clearance for thermal stops (angle) movement
- *- - - - -* .. .. ll'II SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 5 of 12 PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME ~JKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation SErai (Cont'd) 2547 (Cont'd) S&W IC 10 Insufficient lateral As-built Remove lateral 11 clearance for 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 support 9 Insufficient lateral & Seismic Modify restraint vertical.clearance Reanalysis 7,8 Insufficient lateral Seismic Modify restraint clearance Reanalysis 2 U-bolt restricts lateral As-built Modify support I 1 movement 22A Anchor stress over allowable Seismic Relocate adjacent Reanalysis restraint 2541 E IC 6,21 Support member over allowable As-built Modify support 7,9 Insufficient lateral Seismic Modify support clearance Reanalysis 2,8 U-bolt restricts lateral As-built Hodify. support 1 movements 2542
,,.r--
E IC 15,23 Support member over allowable As-built Modify support
!1 13,17 Insufficient lateral clearance Seismic Modify support Reanalysis
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 6 of 12
~.
PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON. FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION 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 Seismic Relocate adja-over allowable Reanalysis cent restraint 11 2560 E IC H-50 U-bolt over Seismic Modify support allowable Reanalysis 2561 E IC H-91 Upward vertical Seismic Modify for restraint required Reanalysis uplift load H-50 U-bolt over allowable Seismic Reanalysis Modify support 11 H-98A Support member As-built Remove vertical over allowable restraint 2544 E IC H-67 Upward vertical Seismic Modify support restraint required Reanalysis for uplift load H-68 Support member As-built Modify Rupport over allowable 2533 E IC H-3 Support member As-built Modify support over allowable 2548 E IC 7 Support member As-built Modify support over allowable 10 Support member As-built Modify support over allowable 12 U-bolt over As-built Modify support allowable 9A Upward vertical Seismic Modify support restraint required Reanalysis for uplift load* 11 Support member As-built Modify support over allowable
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 7 of 12 PIPE SUPPORT HARDWAP.E MODUICATION SUHMARY SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTA!lLE PROBLEM NUMBER RESPONSIBILITY LOCATIOU NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation SErai (Cont'd)
- .!548 {Cont'd) E IC 8 Support member over. allowable As-built Hodify support I1 2545 E IC 3 Support member As-built Modify support over allowable 14 Upward vertical Seismic Modify restraint restraint required Reanalysis for uplift load 2 U-bolt over
- As-built Hodify support allowable 4 ::iupport member As-built Modify support over allowable 7 Support member As-built Modify support over allowable 10,15 Weld over allowable As-built Add weld 6,8 Support member As-built Hodify support over allowable
- .!744 E QC 2,3 Loads out of spring As~built Two- rigid re-range straints re-placed by springs 1 Local pipe wall tieismic Modify support stress over allow- Reanalysis 1
able 2745 E oc 4 Upward vertical Seisruic Modify support restraint required Reanalysis 3 Support does not al- As-built Modify support
.:751 QC low lateral movement I 1 K 2 Local pipe wall Seismic Modify support stress over Reanalysis allowable L753 E oc 1 Support member As-built Hodify support over allowable
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 8 of 12 PIPE SUPPORT HARDWARE MODIF!CATION
SUMMARY
SYSTEM MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation SEra::t: (Cont'd) 2754 E OC 1 Support member As-built Modify support over allowable 2755 E oc 7,8 Upward vertical Seismic Modify support restraint required Reanalysis for uplift load 9 Upward vertical *Seismic Redesign support restraint required Reanalysis for uplift load 11 Weld over allowable As-built Add weld 2756 E IC 54,55 Support member A,;-built Modify support over allowable 2757 E IC H-90 Upward vertical Seismic Modify support for restraint required Reanalysis uplift load H-63, Support member As-built Modify support H-88 over allowable Main. Steam 2577 S&W IC 1 Local stress ex- As-built Modify. lug ceeds allowable 9 Local- stress ex- As-built Replace lug with ceeds allowable clamp 25}9 S&W IC 1 Spring variability SeiRmic. Replace spring ratio exceeded Reanalysis 4 Loads outside Seismic Replace spring spring range Reanalysis 5 Spring variability Seismic 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 Replace springs, range, local over- Reanalysis modify lug stress in lug
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet !la of 12
~
PlPE SUPPORT HARDWARE HODIFICATION
SUMMARY
SYSTEM !!KS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSlllILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Hain Steam (Cont'd) 2346 (Cont'd) S&W oc 5,7,9 Snub be rs, local Seismic ;,1odify snubbers stress,. and sup- Reanalysis and lugs port members are overstressed
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 9 of 12 PIPE SUPPORT HARDWARE MOD1FICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT . REASON FOR ATTRIBUTABLE 11 PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION I
'I Feedwater !
2569 S&W IC. 2,3 Loads outside spring Seismic Replace springs range Reanalysis 6 Thermal movement As-built Reduce pin-to pin dimension 7 Insufficient clearance Seismic Modify support for lateral movement Reanslysis 2571 S&W IC 5 Loads outside spring Seismic Replace springs range Reanalysis Auxiliary Feedwater 2473 E IC 8,18 Lateral clearance in- Seismic Modify sufficient Reanalysis restraint 14 Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 16 Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 11,13,26,29,32 Weld over allowable As-built Modify support 22 Support member over allowable. As-built Modify support 28,31 Support member over As-built Modify support allowable 2683 E OC H-8A U-bolt over allowable As-built Modify support H-11 U-bolt over allowable As-built Modify support H-9 Support member over AR-built Modify support allowable H-1(118Gl), Local pipe wall stress Seismic Modify support H-5(118Gl) over allowable Reanalysis H-4 U-bolt over allowable As-built Modify support H-5(118G2) Upward vertical restraint Seismic Modify support required Reanalysis l-1
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 10 of 12 PIPE SUPPORT HARDWARE MCWIFICATION
SUMMARY
SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Auxiliary Feedwater (Cont'd) 2683 (Cont'd) E QC H-1(118G2) Support does not allow As-built Modify support lateral movement P*ressurizer Spray and Relief 2771 E IC 33 Upward vertical restraint Seismic Modify support required Reanalysis for uplift load 5,23 Weld over allowablf! As-built Add weld 6,24 Support member over As-built Modify support 11 allowable 26,27 Upward vertical restraint Seismic Modify for uplift required Reanalysis load 2000 E IC . 4,12,H-5,8,10,17 Local pipe wall stress over allowables Seismic Reanalysis Modify support 11 15 Insufficient vertical Seismic Modify support clearance Reanalysis 13 Support restraints lateral As-built Modify support - movement 4A,7 ,H-lA, Support member over As-built Modify support ll,ZlA,113 allowable H-2 Weld over allowable As-built Add weld 1 Residual Heat Removal 2508A/2508B E IC H-36,H-15,H-17 Support member over As-built Modify support allowable H-12 Vertical support not Seismic Remove support required Reanalysis 2540B E IC 20,21 Upward vertical restraint required Seismic Reanalysis Modify for uplift load 11
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 NUMBER MODIFICATION TO RESOLUTION Residual Heat Removal (Cont'd) 1 2540B (Cont'd) E IC 23 Insufficient lateral clearance Seismic Modify support Reanalysis 22 Support member over allowable As-built Modify support 2554 E ex: H-31 Insufficient lateral Seismic Modify support clearance Reanalysis
.i Service Water 2465 E IC 1 Support member over As-built Modify support allowable 2467 E IC 1 Support member over As-built Modify support allowable 2471 E IC 2 Local pipe wall stress Seismic Modify support over allowable Reanalysis Component Cooling 2601 E IC H-:-32A,H-28,H-44 Uplift vertical Seismic Modify support for restraint required Reanalysis uplift H-30 Insufficient lateral Seismic Modify support clearance Reanalysis H-31 Weld over allowable As-built Add weld 2603 E IC 4 Insufficient lateral clear- Seismic Modify support ance Reanalysis 1
6,8 Support member over allowable As-built Modify support 9 Upward vertical restraint Seismic Modify support for requir_ed Reanalysis uplift load 10 Upward vertical restraint Seismic Modify support for required Reanalysis uplift load 2604 E IC H-38A Upward vertical restraint Seismic Modify support for required Reanalysis uplift load
SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 12 of 12 PIPE SUPPORT HARDWARE M01'IFICATION SUilllARY SYSTEH NANE MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUHBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Component Cooling (Cont'd) 2604 (Cont'd) E IC H-38B Upward vertical restraint Seismic Modify support for 11 required Reanalysis uplift load H-35,H-36,H-38C Weld over allowable As-built Add weld 11 H-38 Support member over allowable As-built Modify support H-38D Local p,ipe wall stress Seismic Modify support over allowable Reanalysis 11 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 load H-25A Upward vertical restraint Seismic Modify support for required Reanalysis uplift load H-23 Weld over allowable As-built Add weld 11 Containment Vacuum 2650 S&W oc 1 Support restraint lateral As-built !1odify support movement 2 Local stress at at-tachment on pipe As-built Move support above elbow and use trun- [ 1 exceeds allowable nion 3 Local stress Seismic Modify support Reanalysis J1 Uigh Pressure Steam To rtux. Feedwater Pump 2862 E oc 3 Support member over As-built Modify support allowable 2369 E oc 5 Support member .over As-built. Modify support allowable
- otes:
*~ Originally Problem No. 27ue*
I SURRY POWER STATION - UNIT 2 I SECTION 5 I SCHEDULE FOR COMPLETION The .status of the reanalysis of those systems subject to Show Cause and the installation of modifications identified as being required by I reanalysis is shown in Table 5-1, Schedule for Completion. the Reanalysis on all systems is complete pending final review. Required I modifications on all lines will be installed prior to start up of the Unit following the Steqlll Generator Replacement Outage. 1 I I I I I I I I . <* I I I I I I 5-1
SURRY POWER STATION - UNIT 2 TABLE 5-1 SCHEDU~OR COHPLETION 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 St;R outage Containment Recirculation Spray E Complete Complete Prior to start-up
. following SGR outage fiUXiliary Feedwater E Complete Complete Prior to start-up following SGR outage Balance of Systems E/S&W Complete Complete Prior to start-up following SGR 1
outage NOTI:S: E EBASCO S&W Stone & Webster S~R Steam Generator Replacement
---- - - -~-- ----=-------
I SURRY POWER STATION - UNIT 2 I SECTION 6 I 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 I included in this stress reanalysis. Each of the main steam lines has two terminal break locations, one at the I containment penetration and the other at the main steam manifold. the risers to the main steam relief valve headers has two terminal break locations, one at the main steam lines, the other at the tee into the main Each of I steam 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 I maximum primary plus secondary stresses. Upon. reanalysis, two additional breakpoints on each of the steam lines were located. One of these points is lol;!ated immediately upstream of the check valve_ (TV-MS201A, TV-MS201B, I TV-MS201C) and the other point is at the elbow just down:;;tream of the check valve. All of these points will be included in the augmented inservice inspection program. I I I I I . ,, I I I I I I 6-1
I SURRY POWER STATION - UNIT 2 I SECTION 7 I CONSERVATISMS The conservatisms applied to the design of the p1p1ng systems for Surry I 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 I follows the design of Unit 1, applying the same conservative criteria with respect to safety systems and system redundancies. I 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). I Paragraphs 7.1, 7.2, 7.3 and 7.4 describe the differences in the conser-vatisms applied to the Unit 2 reanalysis. I 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 I are independently verified by Surry Power Station quality control personnel. 7.2 QUALITY ASSURANCE/ENGINEERING ASSURANCE I 7.2.1 EBASCO QUALITY ASSURANCE I The EBASCO QA Topical Report ETR-1001, Revision 7, as approved by the Nuclear Regulatory Commission on December 15, 1978, 1s being applied to the Surry Unit 2 reanalysis activities. I 7.2.2 STONE & WEBSTER QUALITY ASSURANCE/ENGINEERING ASSURANCE The Stone & Webster Quality Assurance program described in the VEPCO ... I June 5, 1979 submittal to NRC, is being applied to the Surry Unit 2 reanal-ysis activities. 7.3 USE OF AMPLIFIED RESPONSE SPECTRA I The use of amplified response spectra was extensively discussed in the June 5, 1979 submittal. The soil structure interaction amplified response I 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 I an amplified response spectra enveloping the acceleration of the mass points spanning the elevation of the piping run. I I 7-1
I I 7.4 SURRY POWER STATION - UNIT 2 CONSERVATISMS APPLIED TO INERTIAL STRESSES I 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 l. 5 for the DBE and 1. 25 for OBE I conditions . I I I I I I I I I I I I I I 7-2
I I SURRY POWER STATION - UNIT 2 SECTION 8 I SYSTEM OPERABILITY EVALUATION This section has been deleted. Since all modifications will be installed I prior to startup following the Steam Generator Replacement Outage, a system operability evaluation is no longer necessary. 1 I I I I I I I I I I I I I I I ~1
I SURRY POWER STATION - UNIT 2 I SECTION 9 I 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. I 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 I 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 I work under IE Bulletin 79-14, a detailed evaluation is performed as part of the IE 79-14 effort. S&W has performed evaluation of branch lines in accordance with Section 6 I of the August 1, 1979 report for Unit 1 (Vepco Serial No. 453A). EBASCO has performed evaluation of some of the branch lines by coding for I the NUPIPE 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 I temperature of the branch line. The seismic anchor movement analysis is performed by applying seismic inertia displacements. The applicable stress intensification factor (SIF) at the branch connection is included in the I analysis. The stresses from both analyses are combined by absolute sum. Allowable stress is considered to be SA. I I I I I I I I* I 9-1
I SURRY POWER STATION - UNIT 2 I SECTION 10 .I 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 I 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: I 1) The validity of support stiffness used in the piping reanalysis when, for example, a vertical trunion is I 2) welded onto a horizontal wide flange. The pertinence of the version of B31.l Code implemented in Control Data Corporations' NUPIPE program, which was I used in the EBASCO reanalysis program.
- 3) The identification of the original loads on support H-15 I 4) in pi-oblem 2538.
The verification of the NUPIPE computer program (benchmark problems). I These concerns are addressed in the following sections. I 10~1 SUPPORT STIFFNESS Th~ original piping analysis of Surry Unit 2 did not consider the actual I 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-I 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 I this type of loading and members modified to resist torsion as required. 10.2 NUPIPE COMPUTER CODE .. ~ I At EBASCO' s
- request,. Nuclear Services Corporation (NSC) conducted a thorough review of the NUPIPE program against the source codes, NSC has determinl!d that all values utilized by the program, but not spec-'
I ified by the user as input, are pertinent to the 1967 and earlier versions of the B31. l Power Piping Code. The code of record for Surry Unit 2 is B31.l 1955 with code class N-7. I 10.~ PROBLEM 2538 - SUPPORT H-15 Problem 2538, a portion of the Low Head Safety Injection System (LHSIS) I was originally analyzed as a hand calculation by S&W; SHOCK 2 was not used, therefore, problem 2538 is not withfn the scope of the Show Cause OrdE!r. In the original analysis, decal loads were applied to the re-I straints in this problem*. These decal loads did not include moments. I 10-1
I I SURRY POWER STATION - UNIT 2 I,n the EBASCO NUPIPE analysis of the portion of the LHSIS within pro-blem 2538, the system was not overstressed. However, the loads iden-I ti~ied by the NUPIPE analysis as existing at hanger 15 pipe wall and support anchor stresses to exceed allowables caused local by an order of magnitude. Support H-15 has b~en modified so that it will relieve I the local overstress conditions. 10.4 BENCHMARK PROBLEMS I EBASCO has performed four pipe stress problems supplied by the NRC to verity the NUPI?E computer program. The results were ,submitted to the staff in the EBASCO letter to Dr M Hartzman dated January 3, 1980 I (Letter Number_VEP/NRC/002). I I I I I I *" I I I I I 10-2
I SURRY POWER STATION - UNIT 2 I I I I .1 I I I APPENDIX A I SYSTEMS AFFECTED I I I I I I I I I A-1
- - - - - - - - ~ - -- - - - ~~- ----------~- - - ~ - ~ - -- - - - - - - - - - ~--
I SURRY POWER STATION - UNIT 2 lhe reanalysis included those safety related lines originally computer-an~lrzed with the SHOCK2 program. The systems line numbers, the associated cqmputer problem numbers, and the flow diagram numbers are listed below. The following table includes all seismically analyzed lines. The figure numbers re-fe+ to the FSAR drawings, and the Surry Unit 2, FM and FP drawings included in Ii I *,Appendix ,B, Responsi- Flow I s;rstem Line No. bilities for Analysis Problem No. MKS No. Diagram No. Low Head 8-SI-214-153 E 2695 127Dl FM-106A I Safety Injection 8-SI-292-153
.8-SI-214-153 E
E 2697 2681 127D2
- 127Kl FM-106A FM-106A 8-SI-292-153 E 2682 127K2 FM-106A I 10-SI-284-152 10-SI-216-153 S&W S&W 2727 2727 2727 127Cl 127Cl 127Cl FM-106A FM-106A FM-106A 8-SI-292-153 S&W I 10-SI-351-153 6-SI-249-1502 10-SI-349-153 S&W S&W S&W 2727 2727 2727
.127Cl 127Cl 127Cl FM-106A FM-106A FM-106A 8-SI-214-152 S&W 2727 127Cl FM:-106A I lO-SI-283-152 10-SI-213-153 S&W S&W 2727 2727 127C2 127C2 FM-106A FM-106A 6-SI-248-1502
- S&W 2727 127C2 FM-106A I 10-SI-352-1502 10:-SI-350-153 10-SI-349-153 S&W S&W S&W 2727 2727 2727 127C2 127C2 127C2 FM-106A FM-106A FM-lGoA 10-SI-348-153 S&W 2727 127C2 FM-!Ot;J\
I 8-SI-214-153 l i-SI-24 7-602 S&W E 2727 2537 127C2
.122Al FM-106A FM-106B 12-SI..,.247-1502 E 2537 122Al FM-106B I 12-RC-324-1502 10-RH-117-1502 E
E 2537 2537 122Al 122Al, FM-106B FM-106B, 117Bl 104A I 12-SI-246-602 12-SI-246-1502 12-RC-323-1502 E E E 2555 2555 2555 122.Dl 122Dl 122Dl F:tv1-106B FM-106B FM-106B 10-RH-116-1502 E 2555 122Dl FM-106B I 6-SI-248.-1502
. 6-SI-249-1502 E
E 2539 2539 122Kl 122Kl FM-106B FM-106B 6-SI-250-1502 E 2539 122Jl FM-106B I 6-RC-321-1502 6-SI-343-1502 12-SI-245-602 E E E 2539 2539 2709 122Jl 122Kl 122Ll FM-106B FM-106B FM-106B I 12-SI-245-1502 12-RC-322-1502 E E 2709 2709 122Ll 122Ll FM-106B FM-106B High Head 10-SI-206-153 E 2689 127Fl FM-106A I S~fety Injection 6-CH-372-152 4-CH-412-152 E E 2735 2735 127Gl 127Gl FM-105B FM-105B 3-CH-373-152 E 2735 127Gl FM-105B I 8-SI-214-153 E 2735 l27G2 106A I A-2
- -- --- ---- - -~~-- --- -----~-- --- - -- - ------------
I SURRY POWER STATION - UNIT 2 I Responsi- Flow bilities Problem MKS Diagram I System High Head Line No. 8-CH-504-152 for Analysis E No. 2735 No. 127Gl, G2 No. 105B Safety 8-CH-317-152 E 2735 127Gl, G2 105B I Injection (Cont'd) 8-SI-217-152 8-SI-292-153 E E 2735 2735 127Gl, 127Gl G2 106A 106A 6-SI-218-152 E 2735 127Gl, G2 105B, 106A I 6-SI-219-152 6-SI-278-152 6-CH-501-152 E E E 2735 2735 2735 127Gl, 127Gl, 127Gl G2 G2 105B, 106A 105B, 106A 105B 6-CH-502-152 2735 I 6-CH-503-152 8-CH-505-152 E E E 2735 2735 127Gl 127Gl 127G2 105B 105B 105B 8-CH-506-152 E 2735 127Gl, G2 105B I 8-SI-207-152 8-SI;...302-152 E E 2735 2735 127G2 127G2 106A 106A 8-SI-170-153 E 2735 127G2 106A I 8-SI-172-153 10-SI-206-153 6-CH-318-152 E E E 2735 2735 2735 127G2 127G2 127Gl 106A 106A 105B 6-CH-319-152 2735 127Gl 105B I Residual 14-RH-101-1502 E E 2508B 117Al FM-104A Heat Removal 14-RH-102-602 E 2508B 117Al FM-104A 1 I 10-RH-104-602 10-RH-105-602 E E 2508B 2508B 117Al 117Al FM-104A FM-104A 12-RH-106-602 E 2508B 117Al FM-104A I 10-RH-107-602 10-RH-108-602 10-RH-109-602 E E E 2508B 2508B 2508A 117Al 117Al 117Al FM-104A FM-104A FM-104A 10-RH-110-602 E 2508A 117Al FM-104A I 12-RH-112-602 14-RH-118-602 E E 2508B 2508B 117A.l 117Al FM-104A FM-104A 12-RH-119-602 E 2508A 117Al FM-104A I 12-RH-112-602 3-RH-113-6 02 E E 2540 2540B 117Bl 117Bl FM-104A FM-104A 4-RH-115-152 10-RH-116-1502 E E 2540B 2540 117Bl 117Bl FM-104A *" FM-104A I1 I 10-RH-117-1502 6-RH-120-152 E E 2540 2540 117Bl 117Bl FM-104A FM-104A 10-RH-137-602 E 2540 117Bl FM-I04A I 6-RH-120-152 E 2554 117Cl FM-104A, 101A 1* I I I A-3
I
*suRRY POWER STATION - UNIT 2 I Responsi- Flow bi lit ies Problem MKS Diagram I System Main Steam Line No.
30-SHP-101-601 for Analysis S&W No. 2577 No. 1000 No. FM-14A 11 30-SHP-102-601 S&W 2588 1010 FM-14A I 30-SHP-103-601
.30-SHP-101-601 S&W S&W 2579 2346 1020 103A FM-14A FM-14A 30-SHP-102-:-601 S&W 2346 103A FM-14A I. '
30-SHP-103-601 30-SHP-124-601 S&W S&W 2346 2346 103A: 103A FM-14A FM-14A FM-14A 30-SHP-123-601 s&w 2346 103A I Feed water 30-SHP-122-601 14-WFPD-117-601 . S&W S&W 2346, 2569 103A 100G FM-14A FM-18A
. 14-WFPD-113-601 S&W 2573 101G FM-18A I 14-WFPD-109-601 S&W 2571 102G FM-18A
. ~1.1,xiHary 6-WAPD-101-601 E 2473 118Al, A2 FM-18A, 18B I Feed water 6-WAPD-102-602 3-WAPD-109-601 E
E 2473 2473 2473 118A2 118Al, 118Al, A2 A2 FM-18A, 18B FM-18A FM-18A 3-WAPD-110-601 E I 3-WAPD-111-601 3-WAPD-112-601 3-WAPD-°l 13-601 E E E 2473 2473 2473 118Al, 118Al, 118Al, A2 A2 A2 FM-18A FM-18A FM-18A 3-WAPD-114-601 E 2473 118Al, A2 FM-18A I
- 6-WAPD-150-601 6-WAPD-151,-601 .
E E 2473 2473 118Al, ll8Al,
-A2 A2 FM-18A, 18B FM-18A, 18B 6-WAPD-101-601 E 2683 118G2 FM-18A, 18B I 6-WAPD-102-601 6-WAPD-103-601 6-WAPD-104-601 E
E E 2683*. 2683 2683 118Gl 118Gl, 118Gl, G2 FM-18A, 18B G2 .FM-18A FM-18A 4-WAPD-105-601 2683 118Gl, G2 FM-18A I 4-WAPD-106-601 4-WAPD-107-601 E E E 2683 2683 118Gl, 118Gl, G2 G2 FM-18A FM-18A 4-WAPD-108-601 E 2683 . 118Gl*, G2 FM.:..18A I 6-WAPD-50-601 6-WAPD-52-601 E E 2683 2683 118Gl, 118Gl, G2** FM-18A, 18B G2 FM-18A,18B I Service Water 24-WS-126-10 24-WS-128-10
.24-WS-130-10 E
E E 2465 2467 2469 119Al 119A2 119A3 FM-21A FM-21A FM-21A 24-WS-132-10 E 2471 119A4 FM-21A I I I I I A-4
I SURRY POWER STATION - UNIT 2 I Responsi-bi lities ProblE;!m MKS Flow Diagram I ~ystem Pressurizer Line No. 4-RC-334-1502 for Analysis E Ne;>. 2000 No. 124Al No. FM-103B Safety and 3-RC-335-1502 E . 2000 124Al FM-103B I Relief 3-RC..:.361-,-1502 6-RC-320-602 E E 2000 2000 124Al 124Al, A2 FM-103B FM-103B 6-RC-362-602 E 2000 124Al, A2 FM-103B -1 12-RC-336-602 6-RC-337-1502 6-RC-338-1502 E E E 2000 2000 . 2000 124Al,
. 124Al, 124Al A2 A2 FM-103B FM-103B FM-103B 6-RC-339-1502 2000 124Al FM-103B I 6-RC-340-602 6-RC~341-602 E
E E 2000
. 2000 124Al, 124Al, A2 A2 FM-103B FM-103B 6-RC-342-602 E 2000 124Al, A2 FM*:)03B I ~ressurizer 4-RC-314-1502 E 2771 125Al FM-103B Spray 4-RC-315-1502 E 2771 125Al FM-103B I HP- ~team to 2-CH-368-1502 4..,.SHP-125-601 E E 2771 2862 125Al 131Al FM7103B FM-14A Auxiliary 3-SHP-132-601 E 2862 131Al FM-14A I Feed water Pump 3-SHP-128-601 3-SHP-131-601 E E 2862 2862 131Al 131Al FM-14A FM-14A 3-SHP-157-601 E 2862 -*. 131Al FM-14A I 4-SHP-126-601
. 3-SHP-129-601 4-SHP-127-601 E
E E 2864 2864 2869. l~lBl 131Bl 131Cl FM-14A FM-14A FM-14A 131Cl FM-14A I 3-SHP-130-601 3-SHP-135-601 E E 2869 2869
- 131Cl FM-14A Containment 10-CS-104-153 S&W 2521 123Al FM-lOlA I and Recir-culation Spray 8-CS-123-153 10-CS-103-153 S&W S&W 2521
. 2523 123Al 123Al FM-lOlA FM-lOlA I
8-cs...:122-153 S&W 2523 123Al FM-lO~A 11 I 10-CS-103-153 8-CS-133-153 10-CS-104-153 S&W S&W S&W 2547 2547 2549 123Cl 123Cl 123C2 FM-lOlA FM-lOlA FM-lOlA-~ 8-CS-134-153 S&W 2549 123C2 FM-lOlA I 10-RS-112-153 E 2546 123Dl FM-lOlA' 8-RS-123-153 E 2546 123Dl FM-lOlA I 10-RS-104-153 8- RS-121-153 E E 2541 2541 123D2 123D2 FM-lOlA FM-lOlA I 10-RS-103-153 8-RS--120""" 153 E E 2542 2542 123D3 123D3 FM-lOlA FM-101A 10-RS-111-153 E 2543 123D4 FM-lOlA I 8-RS-122-153 E 2543 123D4 FM-lOlA I I A-5
I
- SURRY POWER STATION - UNIT 2 I Responsi- Flow biHties Problem MKS Diagram I System Containment Line No.
10-RS-112-153 for Analys;i.s E No. 2560 No. 123El No. FM-101A and Recir- 10-RS-104-153 E 2561 123E2 FM-101A I culation Spray (Cont'd) 10-RS-110-153 10-RS-109-153 E E 2544 2533 123Gl 123G2 FM-lOlA FM-lOlA 10-RS-103-153 E 2548 123Hl FM-101A I 10-R$-lll-153 8-CS-134-153 E E 2545 2744 123H2 123Jl FM-lOlA FM-lOlA
- s. . cs-133-153 E 2745 123Kl FM-lOlA I 12-CS-102-153 12-CS-101-153 10-RS-109-153 E
E E 2753 2754 2751 12311. 123Ml 123Nl FM-lOlA FM-lOlA FM-lOlA 4-RS-114-153 E 2751 123Nl FM-lOlA I 10-RS-110..-153 E 2752 123N2 FM-lOlA 4-RS-115-153 E 2752 123N2 FM-101A I 8-CS-133-153 8-CS-134-153 E E 2755 123Pl FM-lOlA 2755 123Pl FM-lOlA 4-CS-135-153 I 4-CS-136-153 4-CS-105-152 E E E 2755 2755 2755 123Pl 123Pl 123Pl FM-lOlA FM-lOlA FM-lOlA 1/2-CS-108-153 E 2755 123Pl FM-lOlA I 4-CS-106-152 10-RS-101-153 E E 2755 2756 123Pl l23Ql FM-101A FM-lOlA I Component 10..-R~-102-153 18-CC-15-121 E E 2757 2604 123Q2 112AA1 FM-lOlA FM-22A Cooling 18-CC-9-121 E 2605 112AB1 FM-22A I 18-CC-7-121 18-CC-14-121 E E 2601 2603 112Sl 112S2 FM-22A FM-22A I Containment Vacmnn 8-CV..-108-151 S&W 2650 137A FM-102A
.~
I I I Note: E = EBASCO I S&W = Stone & Webster I I A,6
I I SURRY POWER STATION - UNIT 2 I I I I I I I I APPENDIX B FLOW DIAGRAMS - I IDENTIFICATION OF PROBLEMS REANALYZED I I I I I I I I B-1
I SURRY POWER STATION~ UNIT 2 I APPENDIX B I FLOW DIAGRAMS - IDENTIFICATION OF PROBLEMS REANALYZED Title Drawing No. I Main Steam 11548-FM-14A I Feed water 11548-FM-lSA Cross-Connects for Auxiliary Feed 11448-FM-lSB I Girculating and Service Water ll 548-FM-21A Component Cooling *11548-FM-22A I Containment and Recirculating Spray 11548-FM-lOlA I Containment Vacuum and Leakage Monitor Reactor Coolant Sheet 1 11548-FM-10 2A 11548-FM-l 03A I Reactor Coolant Sheet 2 *11548-FM-103B Residual Heat Removal 11548-FM-~04A I Chemical and Volume Control Sheet 2 ll548-FM-105B I Safety Injection Sheet 1 Safety Injection Sheet 2 11548-FM-106A ll548-FM-106B I Refueling Water S~qrage Tank Crosstie 11448-FM-106C I I I I I I B-2 I
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I SURRY POWER STATION - UNIT 2 I I I I I* I I I APPENDIX C I IE i RESPONSE TO BULLETIN 79-04 I I I I I I I I I C-1
11 I I SURRY POWER STATION - UNIT 2 APPENDIX C
,)
I RESPONSE TO IE BULLETIN 79-04 Velan swing check valves, sized 3 and 6 inches, are inst al led in the I following seismic Category I piping syst*ems: a) Chemical and volume control system I b) Safety injection systems A detailed listing by line number is contained in the following table. I Iiines with 6 inch check valves were originally seismically analyzed by computer prograill- or hand calculations. The re-evaluation. of these systems I using the correct valve weight is currently being done t,tnder the NOPIPE program. The results have shown that the pipe stress is within the allow-abJ.e for all lines. I Lines with 3 inch check valves were tions. An estimated weight, overly analyzed originally by hand calcula-conservative, was used instead of actual valve weights. The inc~rrect valve weight has no effect on th_ese I calculations and re-evaluation is not the related pipe lines are included required, however, these valves and in the scope of IE Bulletin 79-14. I I I I I I I I I I C-2
I SURRY POWER STATION - UNIT 2 I LISTING OF VELAN SWING CHECK VALVES I COVERED BY IE BULLETIN NO. 79-04 SAFETY INJECTION SYSTEMS - UNIT 2 I 6 Inch 2-SI-79 2-SI-82 6-RC-317-1502 6-RC-319-1502 2-SI-85 6-RC-320-1502 I 2-SI-88 2-SI-91 6....;RC-318-1502 6-RC-3l6-1502 2-SI-94 6-RC-321-1502 I . 2-SI-228 2-SI-229 2-SI-238 6-SI-249-1502 6-SI-249-1502 6-SI-248-1502 2-.SI-239 6-SI-249-1502 I 2-SI-240 2-SI-241 6-SI-250-1502 6-SI-345-1502 2-SI-242 6-SI-344-1502 I 3 Inch 2-SI-243 2-SI-224 6-SI-353-1502 3-SI-346-1503 I 2-SI-225 2-SI-226 2-SI-227 3-SI-270-1503 3-SI-347-1503 3-SI-272-1503 1* CHEMICAL AND VOLUME CONTROL SYSTEM - UNIT 2 3 Inch 2-CH-196 3-CH-500-1502 I 2-CH-258 2-CH-267 2-CH-276 3-CH-381-1503 3-CH-302-1503 3-CH-303-1503 2-CH-309 3-CH-379-1503 I 2-CH-312 3-CH-301-1502 I I I I I I I C-3
,I SURRY POWER STATION - UNIT 2 I ,I I 'I I I I I APPENDIX D I CORRESPONDENCE WITH THE NRG I I I I I I I I I D-1
I SURRY POWER STATION - UNIT 2 I APPENDIX D I CORRESPONDENCE WITH NRC The following is a listing of correspondence with the NRC related to the I reanalysis effort. Item No. Date Signature Addressee Letter No./Subject I NRC TO VEPCO I 1 2 3/13/79 4/2/79 Denton Stello Proffitt Proffitt Show Cause Order Addendum to Show Cause Order I 3 4/13/79 Stello *Proffitt Use of Soil Structure Interaction Techniques I 4 5/18/79 Stello Proffitt Request for Further SSI Information I 5 5/25/79 Eisenhut Proffitt Factor Adjustment to SSI Calculated Stresses I 6 7/18/79 O'Reilly Proffitt Information Pertaining to IE Bulletin No. 79-14, Revision 1 I 7 8/15/79 O'Reilly Proffitt Letter of Guidance on IE Bulletin No. 79-14 I 8 8/27/79 Denton Proffitt Lifting of Suspension Required by the Order to Show Cause I 9 10/5/79 O'Reilly Proffitt Confirmation of Concur-rence I 10 10/23/79 Murphy Proffitt Refers to NRC Inspection. of Sept. 10-13 and Sept. 19-21, 1979 I 11 10/24/79 Murphy Proffitt Refers to NRC Inspection of Sept. 13-14, 1979 I 12 10/25/79 Murphy Proffitt Refers to NRC Inspection of Sept. 26-28, 1979 I 13 11/15/79 Eisenhut Proffitt Refers to Soil Structure Interaction I I D-2
I SURRY POWER STATION - UNIT 2 I APPENDIX D (Cont'd) I Item CORRESPONDENCE WITH NRC I No. Date Signature Addressee VEPCO TO NRC Letter No./Subject I 14 3/30/79 Spencer Denton/ Stello 198/Initial Response to Show Cause Order I 15 16 4/19/79 4/23/79 Stallings Spencer O'Reilly O'Reilly 270/LER 79-010/013L-O 289/Response to IE Bulletin No. 79-07 I 17 4/24/79 Spencer O'Reilly 288/Response to IE Bulletin No. 79-07 I 1~ 4/27/79 Spencer Denton/ 311/Transmittal to Two Stello Sample Problems to EG&G I 19 5/2/79 Stallings Denton Observations on Reanalysis Effort I 20 5/2/79 Spencer Stello 260/Submittal of SSI Information I 21 5/22/79 Ragone Hendrie Comments on Moratorium/ Surry Reanalysis I 22 5/24/79 Spencer Stello Response to NRC Letter of 4/2/79 23 5/24/79. Spencer Stello Response to NRC Letter I of 5/18/79 24 6/5/79 Spencer Denton Submittal of Report on I 25 6/8/79 Spencer Denton Reanalysis Additional Information, Report on Reanalysis I of Piping 26 6/8/79 Spencer Stello Soil Structure Interac-I tion Report 27 6/12/79 Spencer Denton Modification Informa-I tion, Reanalysis of Piping Systems I D-3 I
I I SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) I CORRESPONDENCE WITH NRC Item I No. 28 Date 6/15/79 Signature Spencer Addressee Denton Letter No./Subject Schedule and Support Information I 29 6/19/79 Spencer Denton Support Modifications I 30 6/25/79 Spencer Denton Support Information, Reanalysis of Piping Systems I 31 8/1/79 Spencer Denton Submittal of Revised Report on Analysis I 32 8/21/79 Spencer Denton Analysis Completion of Designated Supports - Outside Containment I 33 8/31/79 Spencer Denton Reanalysis of Piping Systems I 34 8/31/79 Spencer O'Reilly 60-Day Response for IE 79-14 1 I 35 9/13/79 Spencer Eisenhut Response to NRC Letter of 5/25/79 I 36 10/3/79 Proffitt Denton Seismic Analysis of Piping Systems Response to NRC Letter I 37 10/4/79 Spencer O'Reilly of 7 /2/79 38 10/4/79 Spencer O'Reilly Response to IE Letter I Spencer O'Reilly Dated 9/7 /79 Extension of IE 39 10/15/79 I 40 10/23/79 Spencer O'Reilly Bulletin 79-14 Deadline Extension of IE Bulletin 79-14 Deadline, Unit 2 I 41 10/30/79 Spencer O'Reilly 120-Day Response to IE 79-14 I 42 11/28/79 Spencer Denton Seismic Analysis of Piping Systems I I D-4
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I I . SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) I CORRESPONDENCE WITH NRC Item I No, Date Signature Addressee Letter No,/Subject 43 12/7 /79 Spencer O'Reilly Response to NRC Letter I 44 12/13/79 Spencer Denton of 11/8/79 Show Cause Order Reanalysis I 45 12/21/79 Spencer O'Reilly Show Cause 60 Days Analysis Completion I 46 2/1/80 Spencer Denton Show Cause Modification Schedule Revision I 47 2/22/80 Spencer Denton Start-up Request for Surry Unit 2 I 48 3/21/80 Spencer Denton Amended Start-up Request for Surry Unit 2 1 I 49 3/28/80 Spencer Denton Show Cause Report Errata for Surry Unit 1 I so 3/22/79 Kennedy S&W to NRC Denton Transmittal of S&W Computer Programs I 51 3/30/79 Jacobs Herring Submittal of Computer Outputs I 52 4/3/79 Jacobs* Bezler Submittal of Benchmark Problem to Brookhaven National Laboratory I 53 4/6/79 Kennedy Denton Transmittal of S&W Computer Programs I 54 4/6/79 Jacobs Stello Plan for Verification of Dynamic Analysis I 55 4/11/79 Jacobs Bezler Codes Submittal of Computer Outputs I 56 4/13/79 Jacobs Stello Update and *Status of Verification Plan for I Dynamic Analysis Codes I D-5
I I SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) I CORRESPONDENCE WITH NRC Item I No, Date Signature Addressee Lette~ No./Subject 57 4/18/79 Jacobs Hartman Submittal of Computer I 58 4/27 /79 Outputs Jacobs Bezler Submittal of Benchmark I 59 4/27 /79 Jacobs Stello Problems Status of Verification Plan for Dynamic I Analysis Codes 60 5/8/79 Rossier Neighbors Draft Outline of SSI-I 61 5/9/79 Kennedy Stello ARS Report Reference SHOCK 0 I 62 5/11/79 Kennedy Stello Program Reference SHOGK 0 Program 1 I 63 5/14/79 Kennedy Denton Proprietary Computer Codes I 64 6/4/79 Jacobs Bezler Submittal of Benchmark Problems I 65 6/12/79 Jacobs Bezler Submittal of Benchmark Problems I 66 9/6/79 Allen Stello Response to NRC Letter of 8/10/79 I 67 9/7 /79 Nelson Ebasco to NRC Hartzman Benchmark Problem VEP/NRC/001 I 68 1/3/90 Nelson Hartzman Benchmark Problem VEP/NRC/002 I I I I D-6}}