Text

Rept on Reanalysis of Safety-Related Piping Sys, Revision 1
	ML19312A383
Person / Time
Site:	Surry
Issue date:	04/11/1980
From:	; EBASCO SERVICES, INC.
To:	;
Shared Package
ML18139A145	List: ML18139A144; ML19312A383;
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	NUDOCS 8004140224
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{{#Wiki_filter:_ .I O REPORT ON THE !I

I REANALYSIS OF I'

SAFETY-RELATED PIPING SYSTEMS 'I I SURRY POWER STATION-UNIT 2 I I VIRGINIA ELECTRIC I AND POWER COMPANY I I REVISION 1

I I

EBASCO SERVICES INCORPORATED g JERICHO, NEW YORK

I 1 -

8t!1'M 22

VIRGfw!A Ex.ucrutc Aws> Powan CourAny Ricumowns,VamoxxxA anest 1 April 11, 1980 [ Mr. Harold R. Denton, Director Serial No. 138B 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:

1 s SHOW CAUSE ORDER REANALYSIS REPORT REVISION N0. 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 " Report on the Reanalysis of Safety Related Piping Systems, Surry Power Station, Unit 2" 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 j 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 coninitment to the NRC Staff (Vepco letter of March 21, 1986, Serial No.138A) to complete the installation of all modifications asscciated 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 j outlined in the February 22 letter. If you have any questions with regard to this submittal, please contact us. Very truly 'ours, W. C. pencer Vice President - Power Station Engineering and Construction Services Attachment cc: Mr. Victor Stello, Director Office of Inspection & Enforcement Mr. James P. O'Reilly, Director Office of Inspection & Enforcement, Region II i [.

g REPORT ON THE F ? REANALYSIS OF ) SAFETY-RELATED ) PIPING SYSTEMS I SURRY POWER STATION-UNIT 2 l h 6 F VIRGINIA ELECTRIC I AND POWER COMPANY ] E lI l l EBASCO SERVICES INCORPORATED JERICHO, NEW YORK B

i SURRY POWER STATION - UNIT 2 l ll L F REPORT ON TiiE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS SURRY POWER STATION - UNIT 2 VIRGINIA CLECTRIC AND POWER COMPANY FEBRUARY 22, 1980 I REVISION 1 APRIL 11, 1980 l B l l l l g EBASCO SERVICES INCORPORATED JERIClio, NEW YORK F L r

[- SURRY POWER STATION - UNIT 2 TABLE OF CONTENTS Section Title Page 1.0

SUMMARY

AND CONCLUSIONS......................... 1-1 2.0 SCOPE OF REANALYSIS............................. 2-1 3.0 P I PE ST RE S S RE SU LT S............................. 3-1 4.0 PIPE SUPPORT RESULTS............................ 4-1 5.0 SCHEDULE FOR COMPLETION......................... 5-1 6.0 HIGH ENERGY LINE BREAKS......................... 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 Ampli fied 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 NU PIPE C omput e r Code.......................... 10-1 10.3 Problem 2538 - Suppcrt 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 Re s pon se to IE Bulle t in 79-04................... C-1 = D Correspondence with the NRC..................... D-1 F L 1-1 ___A_.________.__A--_m

[ SURRY POWER STATION - UNIT 2 i SECTION 1 l

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 systema 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-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 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 (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-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 modif1 cations, 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 supportsbothinsideandoutsidecontainmentaffectedbytheOrderf1 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-arator 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 modifications are the result of differences between the original design conditions and the actual field as-built condition. I During the reanalysis of Surry Unit 2, 79 stress modifications (22 due to pipe stress, 57 due to nozz 'e overload) and 258 pipe support modifications were identified; while 63 pipe stress and 66 pipe support modifications were identified on Surry Unit 1. - The differences in the number of modif-ications is not considered significant, due to the conduct of the re-analysis applied to Surry Unit 2. Modifications on Surry Unit I were ( l-1 L F w

l [ l SURRY POWER STATION - UNIT 2 identified after ' many analytical iterations; whereas, on Surry Unit 2 modifications were designed based on fewer iterations. The cond uc t of the 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 Proj ect. In addition, the Sur ry Unit 2 reanalysis included the OBE 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 scope and other piping, supports were added to facilitate the NUPIPE re-analysis. 1 [ [ [ <k 1-2 t

SURRY POWER STATION - UNIT 2 SECTION 2 SCOPE OF REANALYSIS As described in the NRC Order to Show Cause, March 13, 1979, some piping 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 & i Webster) and Ebasco Services Incorporated (EBASCO) using a NUPIPE com-puter code. Responsibility for the reanalysis is also identified in Appendix A by system and problem number. The results of the reanalysis are compared with code allowable pipe stresses, allowable loads for nozzles add penetrations, and are used in the evaluation of pipe supports. [ u 2-1 t 6

SURRY POWER STATION - UNIT 2 SECTION 3 PIPE STRESS RESULTS 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 strese 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 I 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. 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, 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). I 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 l (SAM) Stress for runs using the SSI-ARS. Even though Table 3-1 reports DBE l results, stress analysis is performed for OBE also and modifications de-signed wherever necessary. l 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 \\ 3-1 t

[ SURRY POV3R 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 o: lginal 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 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 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 f actor 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 l1 { 22 added. modified, or deleted supports. The modifications include those necessary to the flexibility analysis of the branch lines. A branch line (Problem No. 2508B) was rerouted as a result of thermal reanalysis, not as l1 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, 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-pected, however, that the number and type of modifications due to the stress and support analysis are correct and final. l l 1 1 i i I 3-2 i H

M 3_ O... O O R.. M i SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet I of 5 PIFE STRESS RE-EVALUATION

SUMMARY

System Name Line Size Pipe Stress (psi) and Reanalysis MKS NPS Original Original New New Problea Number, Responsibility Number (Inches) Total Seismic Total Seismic Allowable Low Head Safety Injection 2555 E 122D1 10,12 12043 NA 7974 2449 30690 2709 E 122L1 12 NA NA 19173 11427 33750 2537/2540/25405 E

122A1, 4,6 12350 NA 2739 883 33750 11781 10,12 2539 E

122J1 6 30368 NA 14771 7330 32985 122K1 t 2727 S&W 127C1 6 21179 NA 24352 17453 33750 127C2 8,10 2681 E 127K1 8 1677 307 1220 185 28485 2682 E 127K2 8 1677 307 1174 164 28485 2695 E 127D1 8 21179 NA 2094 1103 28485 2697 E 127D2 8 21179 NA 1981 1022 28485 High Head Safety Injection 2689 E 127F1 10 24649 NA 11773 9571 33750 2735 E 127C1 3,4,6, NA NA 26660 17772 33750 127G2 8,10 Containment and Recirculation Spray 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 19739 33561 2546 E 123D1 8,10 3528 1576 8892 7328 28800 2541 E 123D2 8,10 3528 1576 18338 16636 28800 2542 E 123D3 8,10 3526 1576 18931 17252 28800

W-W-E W E'- W E-W W G_ I SURRY POW 2k STATION - th1T 2 TABLE 3-1 Sheet 2 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) Total Seismic Total Seismic Allowable Containment and Re-circulation Spray (Cont 'd) 3543 E 123D4 8,10 3528 1576 8498 6988 29970 2560 E 123E1 10 7334 NA 12775 10995 29970 2561 E 123E2 10 7334 NA 6587 3576 29970 2544 E 123G1 10 11605 7922 2912 1181 28485 2533 E 123c2 10 11605 7922 5874 3813 28485 2548 E 123H1 10 15785 11241 3904 2437 29970 2545 E 123H2 10 15785 11241 2397 676 29970 3744 E 123J1 8 7966 5118 16143 15187 35820 2745 E 123K1 6 24843 22577 15621 12559 33750 2753 E 123L1 12 6136 2818 1344 394 33750 3754 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 28485 1 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 2686 28485 2757 E 123Q2 10 5810 NA 3847 2381 28485 Main Steam 2577 S&W 100D1 30 13824 NA 10763 2883 33750 2568 S&W 101DI 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

O G.. R O O SURRY POWER STATION - UNIT 3 TABIE 3-1 Sheet 3 of 5 Pi?.* S?dESS RE-EVALUATION

SUMMARY

System Name Line Size Pipe Strees (poi) and Reanalysie NKS NPS Original Original New New Problem Number Responsibility Number (Inches) Total Seismic Total Seismic Allowable l Feedwater 2569 S&W 100G1 14 14499 NA 13681 9360 27000 2573 S&W 10!G1 14 16025 NA 12970 8376 27000 2571 S&W 102G1 14 17927 m 14230 8443 27000 Auxiliary Feedwater 2473 E ll8Al 3,6 8568 2407 20963 17736 27000 Il8A2 2683 E Il8CI 4,6 21230 NA 12988 9188 27000 118G2 Pressuriser Spray 2771 E 125Al 4 18560 NA 8013 3088 30690 Pressuriser Safety and Relief 2000 E 124A1 3,4 9093 NA 8824 5421 30636 124A2 6.12 Residual Heat Removal 2540/2540B E 1.ieted Under k w Head Safety Injection System 2508A/2508B E Il7Al 10,12,14 NA NA 13112 8461 24570 2554 E 117C1 6 E NA 12008 8824 29970 Service Water 2465 E I!9Al 24 NA NA 6529 6212 21600 2467 E 119A2 24 NA NA 6561 6214 21600

7 N O_ M_ I R_ I SURRT POWER STATION - UNIT 2 TABl.E 3-1 Sheet 4 of 5 PIPE STRESS RE-EVALUATION SUMMART System Name Line Size Pipe Stress (psi) and Resnalysis MKS NPS Original Original New New Problem Number Responsibility 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 11614 21600 Component coolina 2601/2603 E 11231 18 9696 NA 7043 5246 21600 11252 2604/2605 E Il2AAl 18 9696 NA 7074 5204 21600 ll2ABI containment vacuum 2650 S4W 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 13151 131Cl ~

.D W D D O_ O .. W .O-O .? SURRY POWER STATION - UNIT 2 TABLE 3-1 Sheet 5 of 5 PIPE STRESS RE-EVALUATION SIDetARY Legend: E = EBASCO S&W = Stone & Webster NA = Not Available Allowable Stress = 1.8 Sh New Total Stress (for SSI/ARS) =Sgp + Spy + 1.5 SDBEI

3DBEA New Seismic (for SSI/ARS)

= 1.5 Sr/sEI

8DBEA New Total Stress (original ARS) = Sg+5DW
IDBEI
IDBEA = Original Total Stress New Seismic (original ARS)

=S DBEI + SDBEA = Original Seismic Stress l1 Where S = Longitudinal Pressure Stress g S = Dead Ioad Stress py SDBEI = Seismic Inertial Stress, Design Basis Earthquake SDBEA = Seismic Stress due to Anchor hovements, Design Basis Earthquake S = Allowable stress at maximum (hot) temperature h 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, j i 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.

SURRY POWER STATION - UNIT 2 { TABLE 3-2 Sheet 1 of 4 N0ZZLE AND PENETRATION

SUMMARY

SHOCK 2 Problems Responsi-Vendor System bility Total No. No. Acceptable Nozzle Confirmation and For of Nozzles / (Evaluation Modification Being Problem No. Analysis Penetrations Complete) Required Obtained Low Head Safety Injection 2555 E 1/0 1 0 1 2709 E 1/0 1 0 0 2537/2540 E 1/0 1 0 1 1539 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 b 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 NA NA 2523 S&W 0/0 NA NA NA 2547 S&W 0/0 NA NA NA 2546 E 0/0 NA NA NA )

L SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 2 of 4 N0ZZLE AND PENETRATION

SUMMARY

SHOCK 2 Problems Re sponsi-Vendor System bility Total No. No. Acceptable Nozzle Confirmation and For of Nozzles / (Evaluation Modification Being Problem No. Analysis Penetrations Complete) Required Obtained Containment and Recirculation Spray (Cont'd) 2541 E 0/0 NA NA NA 2542 E 0/0 NA NA NA 2543 E 0/0 NA NA NA 2560 E 1/0 1 0 0 2561 E 1/0 1 0 0 { 2544 E 1/0 1 0 0 2533 E 1/0 1 0 0 2548 E 1/0 1 0 0 2545 E 1/0 1 0 0 2744 E 0/0 NA NA NA { 2745 E 0/0 NA NA NA 2753 E 1/0 1 0 0 2754 E 1/0 1 0 1 1 2751 E 2/0 2 0 0 [i 2752 E 2/0 2 0 0 2549 S&W 0/0 NA NA NA 2755 E 2/0 2 0 2 2756 E 2/0 2 0 0 2757 E 2/0 2 0 0

[ SURRY POWER STATION - UNIT 2 TABLE 3-2 Sheet 3 of 4 N0ZZLE AND PENETRATION

SUMMARY

SHOCK 2 Ptoblems Responsi-Vendor System bility Total No. No. Acceptable Nozzle Confirmation and For of Nozzles / (Evaluation Modificatica Being Problem No. Analysis Penetrations Complete) Required Obtained Main Steam 2577 S&W 1/1 1/1 0/0 0/0 2588 S&W 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 NA 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 1 1 Residual Heat ( Removal 2540 E (Listed under Low Head Safety Injection System) { (

SURRY POWER STATION - UNIT 2 TABLE 3 2 Sheet 4 of 4 N0ZZLE AND PENETRATION

SUMMARY

SHOCK 2 Problems L Responsi-Vendor System bility Total No. No. Acceptable Nozzle Confirmation and For of Nozzles / (Evaluation Modification Being Problem No. Analysis Penetrations Complete) Required Obtained Residual Keat Removal (Cont'd] 2540B E 0/0 NA NA NA 2508A/2508B E 8/0 8 0 8 2554 E 0/0 NA NA NA l Service Water 2465 E 1/0 1 0 0 2467 E 1/0 1 0 0 2469 E 1/0 1 0 0 l 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 l Containment I-Vacuum 2650 S&W 0 NA NA NA HP Steam to Auxiliary Feedwater Pump 2862/2864/2869 E 1/0 1 0 0 NOTES: NA = Not Applicable E = EBASCO S&W = Stone & Webster I

SURRY POWER STATION - UNIT 2 TABLE 3-3 Sheet 1 of 2 PIPE STRES9 HARDWARE MODIF1tATION

SUMMARY

System Name Reanalysis MKS Attributed and Problem No. Re s ponsibilit y Overstressed Condition To: Re solut ion No. of Modifications low Head Safety Injection 2709 E 122L1 Seismic overstress Seismic Spring hanger replaced 1 Reanalysis by rigid restraint. 2537/2540 E 122Al Thermal overstress Aa-built Removed a restraint, 2 11751 anchor replaced by restraints and a snubber. 2539 E 122J1 Thermal overstress Aa-built Removed a restraint 1 122K1 (Branch Line) Containment and Recirculation Spray 2549 S&W 123C2 Pipe contacts crane Seismic Lateral support added. I wall during seismic Reanalysis condition. 2544 E 123Cl Thermal overstress As-built Removed a restraint. I 2745 E 123K1 Seismic anchor move-As-built vertical restraints 2 ment overstress replaced by spring hangers at two loca-tions 2752 E 123N2 Thermal overstress As-built Bemoved a restraint. 1 (Branch Line) Pressurizer Spray 2771 E 125Al Seismic overstress As-built Two restraints added. 2 Residual Heat Removal 25088 E Il7Al Thermal overstress As-built Rerouting of 1-1/2 in. 1 l1 Branch line pipe 2540 (Listed under Low Head Safety Injection System)

O O O .O O O. O O O . W. O W. W O_ .O SURRY POWER STATION - UNIT 2 TABLE 3-3 Sheet 2 of 2 PIPE STRESS HARDWARE MODIFICATibN

SUMMARY

-System Name Reanalysis MLS Attributed and Problem No. Responsibility Overstressed Condition To: Besolution No. of Modifications Residual Heat Removal (Cont'd) 25405 E 1178 Thermal and seismic As-built Anchor replaced by 2 overstress vertical restraint, horizontal restraint removed. Component Coolina 2604/ ~~ E ll2AAl Seismic overstress Seismic Two restraints added. 2 2605 ll2ABI Reanalysis HP Steam to Auxiliary Feedwater Pump 2862/ E 13]Al Thermal and seismic As-built / Two anchors replaced 5 2864/ 13151 overstress Seismic by restraints, two 2869 131C1 Reanalysis snubbers and a spring

added, Feedwater 2569 S&W 100G1 Insufficient branch As-built Remove existing I

line flexibility U-bolt on 3/4 in. line Notes: E = ESASCO S&W = Stone & Webster

i M M .M M M M ..D M G W M M .M G F SURRY POWER STATION - UNIT 2 TABLE 3-4 Sheet 1 of 2 HARDWARE MODIFICATION SLhMARY DUE TO NOZZLE AND PENETRATION OVERLOADING System Name Reanalysis Attributed and Problea No. Responsibility Equipment No. To: Resolution ho. of hodifications [ Iow Head Safety Injection L 2555 E 2-SI-TE-1B As-built / One restraint 2 g Seismic added, One spring hanger t Reanalysis replaced by a two direction restraint HiRh Head Safety Injection 2735 E 2-CH-P-1A Seismic Ten restraints added, 13 2-CH-P-15 Reanalysis one vertical restraint 2-CH-P-1C replaced by spring hanger, two anchors added Containment and Recirculation Spray 2544 E 2-RS-E-ID Aa-built One restraint removed 1 2533 E 2-RS-E-IC As-built Two restraints added 2 2753 E 2-CS-P-IB As-built / One vertical restraint 3 Seismic replaced by spring Reanalysis hanger, two restraints added 1754 E 2-CS-P-1A As-built / One vertical restraint 2 Seismic replaced by spring Beanalysis one horizontal restraint added. 2751 E 2-RS-P-2A Seismic One restraint added 1 Reanalysis 2752. E 2-RS-P-25 Seismic One restraint added 1 Reanalysis 2755 E 2-CS-P-1B As-built / One restraint added 3 2-CS-P-1A Seismic two vertical restraints Reanalysis removed. 2756 E 2-RS-E-IA As-built One anchor and one 2 2-RS-P-IA restraint removed a

W W W W W W M M M M M M M WC SURRY POWER STATION - UNIT 2 TABLE 3-4 Sheet 2 of 2 HARDWARE MODIFICATION

SUMMARY

DUE TO N0ZZLE AND PENETRATION' OVERLOADING System Name Reanalysis At t ribu t ed and Problem No. Responsibility Equipment No. To Resolution No. of Modifications Containment and Recirculation Spray (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 horieontal 5 2-FW-P-3B Reanalysis and two vertical 2-FW-P-3A rest raint s 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 25088 E 2-RH-P-IA 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-R S-E-I D As -bu il t One restraint removed 1 Com ponent Cooling 260l/2603 E 2-Ril-E-1B As-built Four vertical restraints 6 Seismic replaced by springs and Reanalysis snubbers, two restraints added. Note: E = EBASCO

SURRY POWER STATION - UNIT 2 SECTION 4 PIPE SUPPORT RESULTS { Table 4-1, Pipe Support Analysis Summary, summarizes the pipe support reanalysis program. Six hundred ninety four (694) supports (467 inside the containment, 218 outside the containment) on lines originally analyzed using Shock 2, were reanalyzed as part of this Show Cause effort. Two hundred i fifty eight (258) hardware modifications (175 inside the containment, 83 outside the containment) have been identified. The modifications identified due to the pipe support reanalysis are listed in Table 4-2, Pipe Support liardware Modification 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 identified, only 109 were the result of seismic reanalysis of the piping systems iden-tified in the Show Cause Order, while 149 were the result of differences 1 identified between the as-built conditions and the original design. These 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 of May 25, 1979, and by a factor of 1.25 for OBE per the NRC letter of November 15, 1979. [ [ [ [ [ E u h 4-1 F

1-R R R. R.... M R_ M .R. _. R._ R._ R _ -- R_ I SURRY POWER STATION - UNIT 2 TAELE 4-1 Sheet 1 of 4 PIPE SUPPORT ANAI.YSIS SLMIARY System Name Total Modifications and Analysis Number of E valuation or Additions Probles Number Responsibility Location Supports Complete Required Low Head Sefety Injection System 2537/2540 E IC 33 33 17 1 2555 E IC 17 17 9 2539 E IC 7 7 5 2681 E OC 4 4 3 2682 E OC 4 4 3 1 2695 E OC 10 10 4 2697 E OC 9 9 6 27u9 E IC 9 9 3 2727 Seu OC 17 17 8 l1 High Head afety Injection System 2689 E OC 5 5 4 2735 E OC 52 52 23 l1 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 Seu IC 4 4 1 2546 E. IC 12 12 6 lg

M N N E M E U O E N SURRY Poh2R STATION - UNIT 2 TABLE 4-1 Sheet 2 of 4 PIPE SUPPORT ANALYSIS SUIDfARY Syste,Name total Modifications and Analysis Number of E valua tion or Additions Problem Number Responsibility

beation, Supports Complete Required Cc tainment and Recirculation Spray (Cont'd) 2541 E

IC 11 11 6 2542 E IC 11 11 4 2543 E IC 12 12 6 1 2560 E IC 4 4 1 ] 2561 E IC 5 5 3 lg ) 2544 E IC 6 6 2 i 2533 E IC 5 i l1 j 2548 E IC 15 15 6 i l 2545 E IC 17 17 9 2744 E OC 4 4 3 2745 E OC 4 4 2 l1 2753 E OC 4 4 1 2754 E OC 3 3 1 2751 E OC 5 5 1 2752 E OC 4 4 0 2755 E OC 8 8 4 1 i 2756 E IC 7 7 2 2757 E IC 9 9 3 l i I

M M M M M e m M M M e e m e m SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 3 of 4 PIPE SUPPORT ANALYSIS SLHMARY Systen Name Total Modifications and Analysis Number of E valuation or Additions Problea Number Responsibility location Supports Complete Required 11ain Steam 2577 S&W IC 9 9 2 2588 S4W IC 2 2 0 2579 S&W IC 5 5 3 2346 S&W OC 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 Auxiliary Feedwater 1 2473 E IC 34 34 12 1 2683 E OC 22 22 8 Pressurizer Spray and Relief 2771 E IC 32 32 7 ) 2000 E IC 29 29 15 l1 Residual Heat Removal i 2508A/B E IC 45 45 4 J 25408 E IC 5 5 4 1 l 2554 E OC 1 1 1 a

mm mm m m M M M M M M M M M E E E E SURRY POWER STATION - UNIT 2 TABLE 4-1 Sheet 4 of 4 PIPE SUPPORT ANALYSIS

SUMMARY

ystem Name Total Modifications and Analysis Number of E valuation or Additions P,roblea Number Responsibility.

Location Supports Complete Required h vice Water 2465 E IC 2 2 1 2467 E IC 2 2 1 2469 E IC 1 1 0 1 2471 E IC 1 1 1 Component Cooling 2601 E IC 16 16 5 2603 E IC 13 13 5 2604 E IC 17 17 7 2605 E IC 17 17 4 i j Containment Vacuum f1 } 2650 S&W OC 3 3 3 i High Pressure Steam ~ ~ ~ ~ ~ ~ to Aux Feedwater Pump 2862 E OC 6 8 1 l1 2864 E OC 3 3 0 2669 E OG 7 7 1 Notes: E = EBASCO S&W = Stone & Webster j IC = Inside Containment OC = Outside Containment 4 .. ~.. -. - -,.., - -. - - - -

W m W W m M M M M M M M M M M M M M 'M SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 1 of 14 s PIPE SUPPORT HARDWARE MODIFICATION SUNMARY SYSTEM NAME MKS AiG ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Low Head Safety Injection System 2537/2540 E IC 2537 E IC 2,4 Local pipe wall stress Seismic !!odify support over allowable Reanalysis l1 6 Support member over allowable As-built Modify support 9 Support does not allow lateral As-built Nodify support g mo vement 2540 E IC 5 Insufficient clearance Seismic Hodify support Reanalysis 7,8,9,10.13,26 Support member over allowable As-built Modify support l1 12,28 Pipe clamp over allowable As-built Modify support l1 17,19 U-bolt over allowable As-built Modify support 1 Weld over allowable As-built Add weld l1 8A Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 2555 E IC 8 Support member over allowable As-built hodify support lg 3 Weld over allowable As-built Add wuld 4,5 Local pipe wall stress over Seismic Modify support [ allowable Reanalysis 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 g 2539 E IC 2 Upward vertical restraint Seismic Modify restraint required Reanalysis for uplift load 1 Upward vertical restraint Seismic Hodity restraint required Reanalysis for uplift load ~

O O N O N O N N N N N N O N SURRY FDWER STATION - UNIT 2 TABLE 4-2 Sheet 2 of 12 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

SYSTEM MAME MKS AND ANALYSIS SUPPORT REASGI FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITT LOCATION NUMBER MODIFICATION TO RESOLUTION low Head Safety Xnjection System (Cont'd) 2539 (Cont'd) E IC H-!** Support member over allowable As-built Modify support l1 3,4 Support member over allowable As-built Modify support 2709 E IC 7 Support member over allowable As-built Hodify support 2,3 local pipe wall stresses over Seismic ledify 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 Ioads out of range of spring As-built Replace spring 14 loads out of spring range Seismie Seplace spring Reanalysis 15 loads out of spring range Seismic Replace spriug - -Eaanalysis 16 loads out of spring range Seismic Replace spring Reanalysis l1 18 loads out of spring range Seismic Replace spring Reanalysis 19 Supports restraint lateral As-built Hodify Support movement 2695 E OC H-50 Support member over allowable As-built Modafy support A-16 Support member over allowable As-built Hodify support C-53 Support member over allowable As-built Hodify support A-17 Support member over allowable As-built Modify support

m e M M e e e e e e ee e e e e M e m SUR5Y pot"E3 STATION - UNIT 2 TABII 4-2 Sheet 3 of 12 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

SYSTEM NAME MKS AND ANALYSIS SUPPORT REASOi FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Tow Hehd Safety Iajection System (Cont'd) 2697 E OC H-49 Support member over allowable As-built Modify support C-7 Support not ac t ing 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 Pbdify support 2681 E OC 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 ovet allowable As-built Modify support 2 Support member over allowable As-built Modify support 5 U-bo lt over allowable As-built Ibdify support High Head Safety Anjection System 2689 E OC C-38,C-39 Support member over allowable Ar - alt 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 Ibdify support l1 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 over allowable Seismic Pbdify support I reanalysis 26 Local pipe will stress Seismic Modify support over allowable reanalysis l1 Containment and Recirculation Spray 2521 S&W IC 2 0-bo lt capacity for side-Seismic Add members to load in insuf ficient Reanalysis resist sidelcad

I M M M M M M M M M M M M M M M M M SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 4 ot 12 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

SYSTEM NAME MKS AhD AM1YSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NLKBER RESPONSIBILITY LOCATION NUMEER MODIFICATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) 2521 (cont'd) S&W IC 3 Frame overstressed with Seismic Modify existing l1 new loads out of springs Reanalysis frase and replace range springs lg 4 U-strap has insufficient Seismic Replace existing capacity Reanalysis strap with new framing 5 Local stress Seismic Eliminate anchor Reanalysis and add' wrt/lat restraint 2523 S&W IC 1 U-bolt capacity for side-Seismic Add members to load is insufficient Reanalysis resist sideload 2 Frame overstressed Seismic Replace existing Reanalysis frame 11 3 Capacity of springs in-Seismic Replace springs sufficient Reanalysis 1 4 U-strap has insufficient Seismic Replace existing capacity Reanalysis strap with new framing 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 I upward load Reanalysis sway strut 6 Insufficient clearance As-built Remove lateral for thermal movement stop P Insufficient lateral As-built Remove lateral clearance for thermal stops (angle) no wme nt l

k i SURRY POWER STATION - UNIT 2 TABLE 4-2 hheet 5 of 12 PIPE SUPPORT HARDWARE HODIFICATION

SUMMARY

SYSTEM NAFE HKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER HODIFICATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) 2547 (Cont'd) S&W IC 10 Insufficient lateral as-built Remove lateral l1 clearance for thermal stops (angle) mo vement 11 Local stress and support Aa-built tiodify 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 Hodify support mo vement 22A Anchor stress over allowable Seismic Relocate adjacent Reanalysis restraint 2541 5 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 tiodify support l1 mo vements 2542 E IC 15,23 Support member over allowable As-built hodify support f1 13,1) Insufficient lateral clearance Seismic Hodify support Reanalysis

E E N E E E E E E E E E E O E E SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 6 of 12 PIPE SUPPORT RARDWARE MODIFICATION

SUMMARY

SYSTEM NAME HKS AhD ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation Spray 2>43 E IC 15.23 Support member As-built Modify support over allowable 12,13,14 Insufficient lateral Seismic Modify restraint clearance Reanalysis 24A Support membe r Seismic Relocate adja-over allowable. Rear.alysis cent restraint l1 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 Seismic Modify support i allowable Reanalysis 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 support 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 l 10 Support member As-built Modify support over allowable 12 U-bolt over As-built Modify support I allowable 9A Upward vertical Seismic Modify support restraint required Reanalysis for uplift load 11 Support membe r As-built Modify support over allowable

~. SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 7 of 12 PIPE SUPPORT HARDWARE MODIFICATION SUF&lARY SYSTEM NAME FSCS AND A LLYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) 2548 (Cont'd) E IC 8 Support member As-built hodify support l1 over allowable 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 tiodify support allowable 4 bupport member As-built Hodify support over allowable 7 Support me.aber As-built Modify support over allowable 10,15 Weld over allowable As-built and weld 6,8 Support membe r As-built Hodify support over allowable 2744 E OC 2,3 Loads out of sprir.y As-built Two rigid re-range straints re-placed by springs 1 Local pipe wall Seismic Modify support stress over allow-Reanalysis g able 2745 E Ot, 4 Upward vertical Seismic Modify support restraint required Reanalysis 3 Support does not al-As-built Modify support low latersl movement 1 4751 E OG 2 Local pipe wall Seismic Modify support stress over Reanalysis allowable 4753 E OC 1 Support nember As-built Modify support over allowable

\\ 5A I O 0. M M M M M M SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 8 of 12 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

SYSTEM MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIF! CATION TO RESOLUTION Containment and Recirculation Spray (Cont'd) l 2754 E OC 1 Support member As-built Modify support over allowable 2755 E OC 7,8 Upward vertical Seismic hodify 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 As-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-bu ilt Modify support H-88 over allowable Mair. 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 2579 S&W IC 1 Spring variability Seismic 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&1. oc 1,2,3 Loads outside spring Seismic Replace springs, range, local over-Reanalysis modify lug stress in lug

50RRY POWER STATION - Uh1T 2 TABLE 4,-2 Sheet ba of 12 PIPE SUPPORT llARDWARE !!ODIFICATION SLMMARY SYSTEM !KS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMLER RESPONSIBILITY LOCATION leu!!BER MODIFICATION TO RESOLLT10h flain Steam (Cont'd) 2346 (cont'd) S&'J OC 5,7,9 Snubbers, local Seismic Modify snubbers stress, and sup-Reanalysis and lugs port members are overstressed e

~ W M M 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 RESPONSIBILITY LOCATION NUM BER MODIFICATION TO RESOLUTION F5edwater 2569 ' S&W IC 2,3 Loads outside spring Seismic keplace springs range Reanalysis 6 Thermal movement As-built Reduce pin-to pin dimension 7 Innufficient clearance Seismic Modify support g for lateral movement Reanalysis 2571 S&W IC 5 Loads outside apring seinmic keplace springs range Reanalysis Auxiliary Feedwater 2473 E IC 8,18 Lateral clearance in-Seismic Modify (I nufficient Reanalynin restraint 14 Lpward vertical rentraint Seismic Modify restraint required Reanalysis for uplift load 16 Upward vertical rentraint Seismic Modify restraint required Resnalysis 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 l1 allowable 2683 E OC h-8A D-bolt over allowable An-built Modify support l1 E-Il U-bolt over allowable As-built Modify support E-9 Support member over As-built Modify support allowable H-1(ll8Cl), Local pipe wall stress Seismic Modify support h-5(!!8Cl) over allowable Reanalynin 1 H-4 U-bolt over allowable An-built Modify support H-5(Il8C2) Upward vertical restraint Seismic Modify support required Reanalysin I

O C. O_ R .R R R R R R R R R R .O I SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 10 of 12 PIPE SUPPORT HARDWARE MQDIFICATION

SUMMARY

SYSTEM NAME MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER FIODIFICATION TO RESOLUTIO:4 Auxiliary Feedwater (Cont'd) 2683 (Cont'd) E OC H-1(118C2) Support does not allow As-built Modify support I lateral movement Pressurizer Spray And Relief l 2771 E IC 33 Upward vertical restraint Seismic Modify support required Reanalysis for uplift load 5,23 Weld over allowab1p As-built Add weld 6,24 Support member over As-tuilt Modify support lI allowable 26,27 Upward vertical restraint Seismic Modify for uplift required Reanalysis load l 2000 E IC 4,12,H-5,8,10,17 Local pipe wall stress Seismic Modify support 1 l over allowables Reanalysis l l 15 Insufficient vertical Seismic Modify support clearance Reanalysis 13 Support restraints lateral As-built Modify support movement 4A,7,H-1A, Support member over As-built Modify support 11,21A,113 allowable H-2 Weld over allowable As-built Add weld 1 R:sidual Heat Removal 2508A/25088 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 lI 2540B E IC 20,21 Upward vertical Seismic Modify for uplift restraint required Reanalysis load

M M M M M M M M SURRY FDWER STATION - UNIT 2 TABLE 4-2 Sheet 11 of 12 PIPE SUPPORT HARDWARE MODIFICATION

SUMMARY

SYSTDI !wtE MKS AND ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLEM NUMBER RESPONSIBILITY LOCATION NUMBER MODIFICATION TO RESOLUTION Residual Heat Removal (Cont'd) 2540B (Cont'd) E IC 23 Inse clent lateral clearance Seismic Modify support Reanalysis 22 Support member.rer allowable As-built Hodify support 2554 E OC H-31 Insufficient lateral Seismic Modify support I clearance p.eanalysis 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-Scismic Modify support ance Reanalysis 6,8 Support member over allowable As-built Hodify support l 9 Upward vertical restraint Seismic Modify support for required 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

M M M M M M e M M M M M M M i I I ( SURRY POWER STATION - UNIT 2 TABLE 4-2 Sheet 12 of 12 PIPE SUPPORT HARDWARE MODIFICATION SDtMARY l SYSTE!! NAME MKS NO ANALYSIS SUPPORT REASON FOR ATTRIBUTABLE PROBLE!! NU!!BER RESPONSIBILITY LOCATION NU?!BER MODIFICATION TO RESOLUTION Component Cooling (Cont'd) 1 2604 (Cont'd) E If E1-388 Upward vertical restraint Seismic Modify support for required Reanalysis uplift load li-35,li-36,ti-38C Weld over allowable As-built Add weld l 11-3 8 Support member over allowable As-built Modify support Il-38D Local pipe wall stress Seismic Modify support over allowable Reanalysis lI 2605 E IC 11 - 2 5 Support member over allowable As-built Modify support it-258 Upward vertical restraint Seismic Modify support for required Reanalysis uplift load li-25A Upward vertical restraint Seismic Modify support for required Reanalysis uplift load 11-2 3 Weld over allowable As-built Add weld containment Vacuum 2630 S&W OC 1 Support restraint lateral As-built !bdify support novement 2 local stress at at-As-built Move support above elbowandusetrun-fg tachment on pipe exceeds allowable nion 3 Local stress Seismic Modify support g Reanalysis liigh Presaure Steam To aux. Feedwater Pump 2862 E OC 3 Support member over As-built Hodify support allowable 2369 l. OC 5 Support member over As-built Modify suppurt allowable

otes

- Griginally Problem :;o. 2708

SURRY POWER STATION - UNIT 2 f SECTION 5 L SCHEDULE FOR COMPLETION Ine 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. Required modifications on all lines will be installed prior to start up of the 1 Unit following the Steam Generator Replacement Outage. C E [ E E [ [ [ [ [ j c L [ i 5-1 ~

I.. R R ..R R R I ( C U _U U U _U C SURRY POWER STATIUN - Lf;IT 2 TABLE 5-1 SCHEDULE FOR LW PLETION Status Reanalysis Stress Support / Restraint hod 111 cation Location of Problem Responsibility Reanalysis , Reanalysis _ Installation Inside Containment Systens E/S&W Complete Complete Prior to start-up following SCR outage Outside Containment Systems Low head Safety Injection E/S&W Complete Complete Prior to start up follcwing S6R cutage liigh head Saf ety injection E Complete Complete Prior to start up following SLR outage Containment Recirculation ' pray E Complete Couplete Prior to start up following SGR outage auxiliary feedwater E Complete Complete Prior to start-up following swr outage calance of Systems E/S&W Complete Complete Prior to start-up following SGR g outage NOTES: L = ESASCO S&W = Stone & Webster %R = Steam Generator Replacement

l SURRY POWER STATION - UNIT 2 W SECTION 6 l I HIGH ENERGY LINE BREAKS l 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. l Each of the main steam lines has two terminal break locations, one at the l containment penetration and the other at the main steam manifold. Each of the risers to the main steam relief valve headers has two terminal break j locations, one at the main steam lines, the other at the tee into the main I s t ea;n header. These terminal breakpoints are predetermined and are not changed as a result of the stress reanalysis. l Two intermediate break locations were originally determined based upon maximtun primary plus secondary stresses. Upon reanalysis, two additional b reakpoints on each of the steam lines were located. One of these points is located immediately upstream of the check valve (TV-MS201A, TV-MS201B, t I 1 TV-MS201C) and the other point is et the elbow just downstream of the check valve. All of these points will be included in the augmented } inservice inspection program. I 1I 1 ll 1l 1 ~ l l I 1 I l 1 I L E 6-1 E l

E 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 VEPC0 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- { vatisnis 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 are independently verified by Surry Power Station quality control personnel. 7.2 QUALITY ASSURANCE / ENGINEERING ASSURANCE 7.2.1 EBASCO QUALITY ASSURANCE The EBASCO QA 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. [ 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

L SURRY POWER STATION - UNIT 2 7.4 CONSERVATISMS APPLIED TO INERTIAL STRESSES In accordance with the NRC lecters of May 25, 1979 and November 15, 1979 F to VEPCO, the seismic inertial stresses and loads computed using the SSI-U ARS have been increased by a factor of 1.5 for the DBE and 1,25 for OBE conditions. E [ E E [ E [ E l F L. E 7-2 F. \\

SURRY POWER ST,NION - UNIT 2 SECTION 8 SYSTD1 OPERABILITY EVALUATION rL This section has been deleted. Since all modifications will be installed prior to startup following the Steam Generator Replacement Outaga, a system 1 operability evaluation is no longer necessary. E r [ [ [ E E E [ E 8-1

I 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. 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. I'. 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 UEt 1 ('iepco Serial No. 453A). EBASCO has performed evaluation of rose of the branch lines by coding for I the NUPIPE program and analyzing it 'or seismic anchor movement and thermal analysis. Engineering judgement is csed in qualifying the branch lines with i 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 ir.ertia displacements. The applicable stress intensification factor (SIF) at the branch connection is included in the analysis. The stresses from both analyses are combined by absolute sum. Allowable stress is considered to be S

A I

I I I I I I I 'I l 9-1

I 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 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: 1) The validity of support stiffness used in the piping reanalysis when, 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 I used in the EBASCO 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.I SUPPORT STIFFNESS The original piping analysis of Surry Unit 2 did not consider the actual I stiffness of the supports. Representative support stif fness was considered during the current reanalysis. I 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 ef fort, anchors have been reviewed for this type of loading and members modified to resist torsion as required. 10.2 NUPIPE COMPUTER CODE At EBASCO's

request, Nuclear Services Corporation (NSC) conducted a

l thorough review of the NUPIPE program against the source codes, NSC l 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. l 5 10.3 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 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. I 10-1

SURRY POWER STATION - UNIT 2 In the EBASCO NUPIPE analysis of the portion of the LHSIS within pro-blem 2538, the system was not overstressed. However, the loads iden-tified by the NUPIPE analysis as existing at hanger 15 caused local 7 pipe wall and support anchor stresses to exceed allowables by an order L of magnitude. Support H-15 has been modified so that it will relieve i the local overstress conditions. { 10.4 BENCHMARK PROBLEMS EBASCO has performed four pipe stress problems supplied by the NRC p to verify the NUPIPE computer program. The results were submitted to L the staff in the EBASCO letter to Dr M Hartzman dated January 3, 1980 (Letter Number VEP/NRC/002). E E F L F L FI L l l u r r 7 10-2

E SURRY POWER STATION - UNIT 2 E E E E E APPENDIX A SYSTEMS AFFECTED E E E E E E c L r L A-1

SURRY FOWER STATION - UNIT 2 The reanalysis included those safety related lines originally computer-analyzed with the SHOCK 2 program. The systems line numbers, the associated computer problem numbers, and the flow diagram numbers are listed below. The { following table includes all seismically analyzed lines. The figure numbers re-fer to the FSAR drawings, and the Surry Unit 2, FM and FP drawings included in l1 Appendix B. Responsi-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 [ S-SI-292-153 S&W 2727 127C1 Fh-106A 10-SI-351-153 S&W 2727 127C1 FM-106A 6-SI-249-1502 S&W 2727 127C1 FM-106A (' 8-SI-214-152 S&W 2727 127Cl FM-106A 10-SI-349-153 S&W 2727 127C1 FM-106A 10-61-283-152 S&W 2727 127C2 FM-106A [ 10-SI-213-153 S&W 2727 127C2 FM-106A L 6-SI-248-1502 S&W 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-lGoA 10-SI-348-153 SG 2727 127C2 FM-104 8-SI-214-153 Si d 2727 127C2 FM-106A 12-SI-247-602 E 2537 122A1 FM-106B { 12-SI-247-1502 E 2537 122A1 FM-106B 12-RC-324-1502 E 2537 122A1 FM-106B 10-RH-117-1502 E 2537

122A1, FM-106B,

[ 117B1 104A 12-SI-246-602 E 2555 122D1 FM-106B 12-SI-246-1502 E 2555 122D1 FM-106B 12-RC-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 i r L 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 s L 3-CH-373-152 E 2735 127G1 FM-105B 8-SI-214-153 E 2735 127G2 106A [ A-2 i

L SURRY POWER STATION - UNIT 2 ( Responsi-Flow L bilities Problem MKS Diagram System Line No. for Analysis No. No. No. { High Head 8-CH-504-152 E 2735 127G1, G2 105B Safety 8-CH-317-152 E 2735 127G1, G2 105B Injection 8-SI-217-152 E 2735 127G1, C2 106A E (Cont'd) 3-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, C2 105B, 106A [ 6-CH-501-15. E 2735 127G1 105B 6-CH-502-15; E 2735 127G1 105B 6-CH-503-152 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 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 Residual 14-RH-101-1502 E 2508B ll7Al FM-104A Heat Removal 14-RH-102-602 E 2508B ll7Al FM-104A y 10-RH-104-602 E 2508B 117Al FM-104A 10-RH-lC5-602 E 2508B 117Al FM-104A [ 12-RH-10 a-602 E 2508B ll7Al FM-104A 10-RH-10/-602 E 2508B ll7Al FM-104A 10-RH-108-602 E 2508B ll7Al FM-104A { 10-RH-109-602 E 2508A 117Al FM-104A 10-RH-110-602 E 2508A Il7Al FM-104A 12-RH-112-602 E 2508B ll7Al FM-104A [ 14-RH-118-602 E 2508B ll7Al FM-104A 12-RH-119-602 E 2508A 117Al FM-104A 12-RH-112-602 E 2540 117B1 FM-104 A 3-RH-113-602 E 2540B 117B1 FM-104A ( 4-RH-115-152 E 2540B 117B1 FM-104A

1 10-RH-116-1502 E

2540 117B1 FM-104A 10-RH-117-1502 E 2540 117B1 FM-104A [ 6-RH-120-152 E 2540 ll7B1 FM-104A 10-RH-137-602 E 2540 117B1 FM-104A 6-RH-120-152 E 2554 117C1 FM-104A, 101A L A-3

SURRY POWER STATION - UNIT 2 Responsi-Flow bilities Problem MKS Diagram System Line No. for Analysis No. No. No. L Meta Steam 30-SHP-101-601 SSW 2577 100D FM-14A l1 30-SHP-102-601 S&W 2588 101D FM-14A 30-SHP-103-601 S&W 2579 102D FM-14A { 30-SHP-101-601 S&W 2346 103A FM-14A 30-SHP-102-601 S&W 2346 103A 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 118A2 FM-18A,18B p 3-WAPD-109-601 E 2473 118A1, A2 FM-18A L 3-WAPD-110-601 E 2473 118A1, A2 FM-18A 3-WAPD-111-601 E 2473 118A1, A2 FM-18A 3-WAPD-112-601 E 2473 ll8A1, A2 FM-18A 3-WAPD-l l 3-601 E 2473 118A1, A2 FM-18A 3-WAPD-114-601 E 2473 118A1, A2 FM-18A 6-WAPD-150-601 E 2473 118A1, A2 FM-18A,18B 6-WAPD-151-601 E 2473 118A1, A2 FM-18A,18B 6-WAPD-101-601 E 2683 118G2 FM-18A,18B 6-WAPD-102-601 E 2683 118G1 FM-18A,18B 6-WAPD-103-601 E 2683 118G1, G2 FM-18A p L 6-WAPD-104-601 E 2683 118G1, G2 FM-18A 4-WAPD-105-601 E 2683 118G1, G2 FM-18A 4-WAPD-106-601 E 2683 118G1, G2 FM-18A 4-WAPD-107-601 E 2683 118G1, G2 FM-18A 4-WAPD-108-601 E 2683 118G1, C2 FM-18A 6-WAPD-50-601 E 2683 ll8G1, G2 FM-18A,ISB 6-WAPD-52-601 E 2683 ll8G1, G2 FM-18A,18B Service Water 24-WS-126-10 E 2465 119Al FM-21A 24-WS-128-10 E 2467 119A2 FM-21A [ 24-WS-130-10 E 2469 119A3 FM-21A 24-WS-132-10 E 2471 119A4 FM-21A [ [ [. A-4 r'

SURRY POWER STATION - UNIT 2 Responsi-Flow [ bilities Problem MKS Diagram System Line No. for Analysis No. No. No. { Pressurizer 4-RC-334-1502 E 2000 124A1 FM-103B Safety and 3-RC-335-1502 E 2000 124A1 FM-103B Relie f 3-RC-361-1502 E 2000 124A1 FM-103B [ 6-RC-320-602 E 2000 124A1, A2 FM-103B 6-RC-362-602 E 2000 124A1, A2 FM-103B 12-RC-336-602 E 2000 124A1, A2 FM-103B 6-RC-337-1502 E 2000 124A1, A2 FM-103B ( 6-RC-338-1502 E 2000 124A1 FM-103B 6-RC-339-1502 E 2000 124A1 FM-103B 6-RC-340-602 E 2000 124Al, A2 FM-103B { 6-RC-341-602 E 2000 124A1, A2 FM-103B 6-RC-342-602 E 2000 124A1, A2 FM-103B Pressurizer 4-RC-314-1502 E 2771 125Al FM-103B [ Spray 4-RC-315-1502 E 2771 125Al FM-103B 2-CH-368-1502 E 2771 125Al FM-103B [ HP Steam to 4-SHP-125-601 E 2862 131A1 FM-14A Auxiliary 3-SHP-132-601 E 2862 131A1 FM-14A Feedwater 3-SHP-128-601 E 2862 13'41 FM-14A Pump 3-SHP-131-601 E 2862 431A1 FM-14A 3-SHP-157-601 E 2862 131A1 FM-14A 4-SHP-126-601 E 2864 131B1 FM-14A l 3-SHP-129-601 E 2864 131B1 FM-14A 4-SHP-127-601 E 2869 131C1 FM-14A 3-SHP-130-601 E 2869 131C1 FM-14A 3-SHP-135-601 E 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 2523 123Al FM-101A 8-CS-122-153 S&W 2523 123Al FM-101A 10-CS-103-153 S&W 2547 123Cl FM-101A 8-CS-133-153 S&W 2547 123Cl FM-101A ( 10-CS-104-153 S&W 2549 123C2 FM-101A. 8-CS-134-153 S&W 2549 123C2 FM-101A E 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 rL h A-5 i

I SURRY POWER STATION - UNIT 2 Responsi-Flow bilities Problem MKS Diagram System Line No. forAnalysp No. No. No. Containment 10-RS-112-153 2560 123El FM-101A l and Recir-10-RS-104-153 E 2561 123E2 FM-101A culation Spray 10-RS-110-153 E 2544 123G1 FM-101A (Cont'd) 10-RS-109-153 E 2533 123G2 FM-101A 10-RS-103-153 E 2548 123H1 FM-101A 10-RS-111-153 E 2545 123H2 FM-101A 8-CS-134-153 E 2744 123J1 FM-101A 8-CS-133-153 E 2745 123K1 FM-101A I 12-CS-102-153 E 2753 123L1 FM-101A 12-CS-101-153 E 2754 123M1 FM-101A 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-115-153 E 2752 123N2 FM-101A 8-CS-133-153 E 2755 123P1 FM-101A 8-CS-134-153 E 2755 123P1 FM-101A i I 4-CF-135-153 E 2755 123P1 FM-101A 4-GS-136-153 E 2755 123P1 FM-101A 4 CS-105-152 E 2755 123P1 FM-101A r 1/';-CS-108-153 E 2755 123P1 FM-101A 4-CS-106-152 E 2755 123P1 FM-101A 10-RS-101-153 E 2756 I?"ql 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 I 18-CC-7-121 E 2601 112S1 FM-22A 18-CC-14-121 E 2603 112S2 FM-22A l I Containment 8-CV-108-151 S&W 2650 137A FM-102A Vacuum I Note: .E = EBASCO S&W = Stone & Webster l l l A-6 l

_m E SURRY POWER STATION - UNIT 2 i E rL E E E l l ireENDIx 3 l FLOW DIAGRAMS - IDENTIFICATION OF PROBLEMS REANALYZED E ru ru B-1 7 l

SURRY POWER STATION - UNIT 2 I i APPENDIX B I FLOW DIAGRAMS - IDENTIFICATION 0F PROBLEMS REANALYZED L Title Drawing No. Main Steam 11548-FM-14A Feedwater 11548-FM-18A Cross-Connects for Auxiliary Feed 11448-FM-18B l Circulating and Service Water 11548-FM-21A I i Component Cooling 11548-FM-22A Containment and Recirculating Spray 11548-FM-101A Containment Vacuum and Leakage Monitor 11548-FM-102A Reactor Coolant Sheet 1 11548-FM-103A Reactor Coolant Sheet 2 11548-FM-103B Residual Heat Removat 11548-FM-104A Chemical and Volume Control Sheet 2 11548-FM-105B Safety Injection Sheet 1 11548-FM-106A Safety Injection Sheet 2 11548-FM-106B Refueling Water Storage Tank Crosstie 11448-FM-106C I I I E <I I

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== vis * < z,, l I s w \\ ine - .:.&ff/g{ n..no...s a A-A .,.2...s.e tes FLOW DI AGR AM ""7 46-122 D; REACTOR COOL ANT SYSTEM "'N". # -h'**d' E f) M SHEET I " f.) I S v.e s.a.va on-ouan.t*owsa essnen ~ w ac c 4= co=== es= = = M#* [ pl* M " E s""",,gy.- F s ac.o.,,oe. su.sms. .. .i A - '1s co. o no. ti :' % es ri 3 = 118348 FM-103 A L :1-e. ~ i( 1

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F'T n'T n'l'l l 'lT ' T 'T' F' T n F' T 'T n a s 4 s i 7 e e, is se la a i sg .~ -#.--.~- p.. pup'=2"* ,u:.v.;u, y-R!

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h...n

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s9_. l_' g.,,,

p,.no.f 8 7, '.'dy _,..:~~.* , T ' =. * ' ~ - * * *

n

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c. <

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d. fees M**hdW 4e FLOW DIAGRAM CHEM & VOLUME CONTROL SYS SHEET-2 e

,we -_-. _ senta

w...,,,d,...,s "

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1"<SM%

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f. c.,,,,.

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r. (n-Sc t.ieos N r c.m.sas.itae iA a tee esse (psi c34)(p.r)

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==

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m. t.,

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x. i, a,,4, %,.y

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- 43**

)

%4 1

, '- G=:.su r.; j q. p,. g c . %g n 4 pm u - m,, _ _ I-' M _ - ) d"7'lJ C.*_* 'Eiwc { L ip.- ~ n n .;~ w: o s ,.g vT,l'" ~ { W: gA o,r "a - "T~ t T,s w;j 3.

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t_ M si rrme a t c.

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q;;,

j um w <t n v.s.m.~.r b ~. -

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"**"7__

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00* Id e s

e...e pp.ge. et s t _e...e j ee.e 4 4-I r e t 9 ? l; t. ti i i. A e-

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SURRY POWER STATION - UNIT 2 E E E E m APPENDIX C RESPONSE TO IE BULLETIN 79-04 E E E E E E i ~ rL C-1 )

I 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 systemc A detailed listing by line number is contained in the following table. Lines with 6 inch check valves were originally seismically analyzed by coaputer program or hand calculations. The re-evaluation of these systems uring the correct valve weight is currently being done under the NUPIPE program. 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-p tions. An estimated weight, overly conservative, was used instead of L actual valve weights. The incorrect valve weight has ne ef fect on these calculations and re-evaluation is not required, however, these valves and the related pipe lines are included in the scop-of IE Bulletin 79-14. E E E cL ru C-2

l { i l 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 { L 2-SI-85 6-RC-320-1502 l 2-SI-88 6-RC-318-1502 l 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-249-1502 { 2-SI-238 6-SI-248-1502 2-SI-239 6-SI-249-1502 2-SI-240 6-SI-250-1502 2-SI-241 6-SI-345-1502 2-SI-242 6-SI-344-1502 2-SI-243 6-SI-353-1502 3 Inch 2-SI-224 3-SI-346-1503 2-SI-225 3-SI-270-1503 2-SI-226 3-SI-347-1503 { 2-SI-227 3-SI-272-1503 CHEMICAL AND VOLUME CONTROL SYSTEM - UNIT 2 3 Inch 2-CH-196 3-CH-500-1502 2-CH-258 3-CH-381-1503 2-CH-267 3-CH-302-1503 ) f 2-CH-276 3-CH-303-1503 2-CH-309 3-CH-379-1503 2-CH-312 3-CH-301-1502 l l l F L FL l l ~ C-3

SURRY POWER STATION - UNIT 2 I iI i l lI

I l

APPENDIX D l coRResPoNDsNcs WITil Tile NRC i i !I !I I lI D-1

SURRY POWER STATION - UNIT 2 APPENDIX D CORRESPONDENCE WITH NRC The following is a listing of correspondence 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 l 2 4/2/79 Stello Proffitt Addendum to Show Cause Order 3 4/13/79 itello ~Proffitt Use of Soil Structure Interaction Techniques 4 5/18/79 Stello Proffitt Request 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 8/15/79 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 0'Reilly Proffitt Confirmation of Concur-rence 10 10/23/79 Murphy Proffitt Refers to NRC Inspection of Sept. 10-13 and Sept. .a 19-21, 1979 g 11 10/24/79 Murphy Proffitt Refers 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 I I ( D-2

I 1 SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITH NRC Item No. Date Signature Addressee Letter No./ Subject VEPCO TO NRC 1 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' Reil ly 289/ Response to IE Bulletin No. 79-07 17 4/24/79 Spencer O'Reilly 288/ Response to IE Bulletin No. 79-07 18 4/27/79 S pencer Denton/ 311/ Transmittal to Two Stello Sample Problems to EG&G 19 5/2/79 Stallings Denton Observations on Reanalysis Effort 20 5/2/79 Spencer Stello 260/ Submittal of SSI In format ion I 21 5/22/79 Ragone Hendrie Comments on Moratorium / Surry Reanalysis 22 5/24/79 S pencer Stello Response to NRC Letter of 4/2/79 23 5/24/79 S pencer Stello Response to NRC Letter I 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 I of Piping 26 6/8/79 Spencer Stello Soil Structure Interac-I tion Report 27 6/12/79 Spencer Denton Modification Informa-tion, Reanalysis of Piping Systems

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 Spencer Denton Support Modifications { 30 6/25/79 Spencer Denton Support Information, Reanalysis of Piping [ Systems 31 8/1/79 Spencer Denton Submittal of Revised ( Report on Analysis 32 8/21/79 Spencer Denton Analysis Completion of Designated Supports -- E Outside Containment i 33 8/31/79 Spencer Denton Reanalysis of Piping p L Systems 34 8/31/79 Spencer O'Reilly 60-Day Response for { IE 79-14 35 9/13/79 Spencer Eisenhut Response to NRC Letter of 5/25/79 { 36 10/3/79 Proffitt Denton Seismic Analysis of Piping Systems 37 10/4/79 Spencer O'Reilly Response to NRC Letter of 7/2/79 b 38 10/4/79 Spencer O'Reilly Response to IE Letter Dated 9/7/79 39 10/15/79 Spencer O'Reilly Extension of IE Bulletin 79-14 Deadline { 40 10/23/79 Spencer O'Reilly Extension of IE Bulletin 79-14 Deadline, Unit 2 41 10/30/79 Spencer O'Reilly 120-Day Response to { IE 79-14 42 11/28/79 Spencer Denton Seismic Analysis of- [, Piping Systems [ D-4 f

[ SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITil NRC Item No. Date SAnature Addressee Letter No./ Subject 43 12/7/79 Spencer O'Reilly Response to NRC Letter of 11/8/79 ( 44 12/13/79 Spencer Denton Sho.i Cause Order Reanalysis { 45 12/21/79 Spencer O'Reilly Show Cause 60 Days Analysis Completion p 46 2/1/80 Spencer Denton Show Cause Modification L Schedule Revision 47 2/22/80 Spencer Denton Start-up Request for ( Surry Unit 2 48 3/21/80 Spencer Denton Amended Start-up Request { for Surry Unit 2 49 3/28/80 Spencer Denton Show Cause Report Errata for Surry Ueit 1 S&W to NRC { 50 3/22/79 Kennedy Denton Transmittal of S&W Computer Programs f 51 3/30/79 Jacobs tierring Submittal of Computer L Outputs 52 4/3/79 Jacobs Bezier submittal of Benchmark ( Problem to Brookhaven National Laboratory { 53 4/6/79 Kennedy Denton Transmittal of S&W Computer Programs p 54 4/6/79 Jacobs Stello Plan for Verification L of Dynamic Analysis Codes { 55 4/11/79 Jacobs Bezler Submittal of Computer Outputs ) 56 4/13/79 Jacobs Stello Update and Status of {- Verification Plan for Dynamic Analysis Codes ~ D-5

~ SURRY POWER STATION - UNIT 2 APPENDIX D (Cont'd) CORRESPONDENCE WITH NRC ltem No. Date Signature Addressee Letter No./ Subject [ 57 4/18/79 Jacobs Hartman Submittal of Computer Outputs 58 4/27/79 Jacobs Bezler Submittal of Benchmark Problems { 59 4/27/79 Jacobs Stello Status of Verification Plan for Dynamic Analysis Codes 60 5/8/79 Rossier Neighbors Draft Outline of SSI-ARS Report 61 5/9/79 Kennedy Stello Reference SHOCK 0 Program { 62 5/11/79 Kennedy Stello Reference SHOCK 0 Program 63 5/14/79 Kennedy Denton Proprietary Computer { Codes 64 6/4/79 Jacobs Bezler Submittal of Benchmark [ Problems 65 6/12/79 Jacobs Bezler Submittal of Benchmark { Problems 66 9/6/79 Allen Stel10 Response to NRC Letter of 8/10/79 Ebasco to NRC 67 9/7/79 Nelson Hartzman Benchmark Problem VEP/NRC/001 { 68 1/3/90 Nelson liartzman Benchmark Problem VEP/NRC/002 b E E-I 1 D-6 -__-__}}

ML19312A383

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ML19312A383

Text

Dear Mr. Denton:

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