ML18116A401
| ML18116A401 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/21/1979 |
| From: | Spencer W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 687, NUDOCS 7908230467 | |
| Download: ML18116A401 (16) | |
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VIRGINIA. ELECTRIC A.ND POWER COMPANY RrcHMOND,VIBGINIA. 28261 August 21, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
Serial No. 687 PSE&C/CMRjr:mac:wang Docket No. 50-280 License No. DPR-32 ANALYSIS COMPLETION OF DESIGNATED SUPPORTS OUTSIDE CONTAINMENT SURRY POWER STATION UNIT 1 The Nuclear Regulatory Commission staff has identified certain supports outside the containment for which analysis must be complete prior to consideration of interim start up of Surry Unit 1.
These supports associated with the low head safety injection system, high head safety injection system, auxiliary feedwater system, and containment and recirculation spray system are identified in Table 4-lB of our August 1, 1979 submittal (Vepco Serial No.
453A).
The purpose of this letter is to inform you that pipe support analysis associated with these systems has been completed.
On this basis, we request immediate consideration of our previous requests for interim operation.
To recap the total pipe support results to date, there are 1030 supports (492 inside containment, 538 outside containment) on lines originally analyzed by SHOCK 2.
All 492 pipe supports within the reactor containment have been reanalyzed, and 51 hardware modifications have been identified. All 112 supports for the four systems identified above which are outside the reactor containment have been analyzed and 10 modifications have been identified.
These modifications are included in the attached revised Table 4-2.
For clarification, we are submitting revised Tables 3-3, 4-lA, 4-lB, and 4-2 originally submitted with our report of August 1, 1979 to reflect completion of the above reanalysis. These tables are completely updated to show results of all analysis work to date.
Modifications associated with the following will be accomplished prior to startup:
- 1.
All modifications shown on Table 3-4, Hardware Modification Summary Due to Nozzle and Penetration Overloading, as submitted wit~ our August 1, 1979 report.
s...
e vrnorn1A ELEcTmc AND PowER coMPANY To Mr. Haro 1 d R. Denton, Director
- 2.
All modifications shown on revised Table 3-3, attached, Pipe Stress Hardware Modification Summary.
- 3.
All modifications shown on revised Table 4-lA, attached, Pipe Support Status Summary Inside Containment - SHOCK 2.
- 4.
All modifications shown on revised Table 4-18, attached, Pipe Support Status Summary Outside Containment - SHOCK 2.
We appreciate your prompt response to our request for interim operation.
If you should have any questions, please contact us immediately.
Attachments:
4 Tables
- Spencer Vice Pres ent - Power Station Engineering and Construction Services 2
Problem MKS No.
No.
System 334B 508 102Gl,G2 FW 540 548A 562 727 735 7;.3 744/7 54 745 746 ll 7Al ll 7Bl 123Bl 123E2 127Cl 127Gl 127Fl 123Jl 123Kl l31Al B2 C3 RHR RHR G&RS C&RS LHSI HHSI LHSI C&RS C&RS HP Steam SURRY POWER STATION, UNIT 1 TABLE 3-3 PIPE STRESS HARDWARE MODIFICATION
SUMMARY
Overstressed Condition Thermal overstress DBET overstressed RHR pump Discharge elbows and overloaded nozzles.
- 1. Thermal overstress due to support which was not included in original analysis.
2, Overstress in 2" line which was not included in original analysis.
DBEI overstress condition DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI ovi,rstress DBEI overstress DBEI overstress l of 2 Attributable To:
As-Built Seismic Reanalysis As-Built As-Built As-Built Seismic Reanalysis As-Built As-Built As-Built As-Built As-Built Revised August-~, 1979 Resolution Delete U-Bol tirn Six supports added to alleviate overstress condition.
- 1. Delete NS & RH's.
- 2. Add Anchor to 2" line.
Addition of a horizontal
- snubber, Addition of EW, Replace RH with SH, Replace SH with VG, Addition of an LSS, Addition of two guides.
Shim existing constraint to VC/LC..
Modification and re-placement of constraints to reflect original analysis.
Modification and re-placement of co~straints to reflect original analysis.
Modification and addition of constraints to reflect original original analysis.
Problem MKS No.
No.
System 488/480 122Al,Cl ccw 5071481 112Bl 1Fl ccw 509A/D 112G ccw 517 112M ccw 526C 1121 ccw 527A/C 112T ccw 605A 112AA ccw 766 112AR ccw 2527/2529 112 ccw NOTE:
SURRY POWER STATION, UNIT 1 TABLE 3-3 (Cont)
Overstressed Condition DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress DBEI overstress and thermal overstress DBEI overstress Attributable To:
As-built As-built As-built As-built Seismic Reanalysis Seismic Reanalysis As-built As-built As-built As-built Revised August 21, 1979 Re 0solution Add two guides to Problem 480 and two lateral restraints to Problem 488.
Add two guides to Problem 481.
Added one vertical restraint.
Eight restraint changes are required. lElOE Added a lateral restraint and modify an SH to a rigid vertical *constraint.
Delete anchor A36 and shim exchanger supports.
Add four lateral restraints.
Add horizontal guides and delete an axial restraint.
Deiete Anchor and Shim exchanger supports.***
- The use 6f ARS curves causes higher acceleration levels than the procedure for below-grade structures formerly used as described in the Seismic Design Review revised September 15, 1971.
- Due to Branch-Line Analysis
- Revised since August 1, 1979 Submittal 2 of 2
Revised e
August 21, 1979 SURRY POWER STATION UNIT 1 TABLE 4-lA PIPE SUPPORT STATUS
SUMMARY
INSIDE CONTAINMENT -
SHOCK 2 Modifica-System Total No.
No. Acceptable tions or and of (Evaluation No. Under Additions Prob. No Supports Complete)
Evaluation Required Comments Low Head Safety Injection 555 14 14 4
706A 10 10 707A 9
9 708 22 22 3
1555 9
9 Containment
& Recircu-lation Spray 525A/1525A 35 35 5
544 12 12 2
- 544A, 6
6 544B 6
6 1
546/560 18 18 6
546/5600 11 11 2
546/5620 11 11 1
547 13 13 548A 2
2 548B 22 22 4
548C 25 25 2
562 19 19 5
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System and Prob. No Main Steam 322A 323A 334A Feedwater 322B 323B 334B Auxiliary Feedwater 417 Pressurizer Spray and Relief 630 636 Residual Heat Removal 508 540 Service Water 465 Revised SURRY POWER STATION UNIT~
TABLE 4-lA (cont'd.)
PIPE SUPPORT STATUS
SUMMARY
INSIDE CONTAINMENT -
SHOCK 2 August 21, 1979 Total No.
No. Acceptable of (Evaluation No. Under Supports Complete)
Evaluation 5
17 3
8 14 8
26 27 33 50 10.
8 5
17 3
8 14 8
26 27 33 50 10 8
2 of 3 Modifica-tions or Additions Required 1
3 1
Comments
System and Prob. No Component Cooling 603A 603B 605A 605B Total No.
of Supports 7
5 17 10 SURRY POWER STATION UNIT 1 TABLE 4-lA (cont'd)
PIPE SUPPORT STATUS
SUMMARY
INSIDE CONTAINMENT -
SHOCK 2 No. Acceptable (Evaluation No. Under Complete)
Evaluation 7
5 17 10 3 of 3 Modifica-tions or Additions Required 3
2 3
2 Revised August 21, 1979 Comments
Revised August 21, 1979 SURRY POWER STATION UNIT 1 TABLE 4-lB PIPE SUPPORT STATUS
SUMMARY
OUTSIDE CONTAINMENT -
SHOCK 2 Modifica-System Total No.
No. Acceptable tions or and of (Evaluation No. Under Additions Prob. No Supports Complete Evaluation Required Comments Low Head Safety Injection 727 21 21 731A 4
4 3
731B 4
4 2
743 5
5 High Head Safety Injection 735 43 43 3
Containment
& Recircu-lation Spray 744/754 10 10 745 8
8 1
751 2
2 Main Steam 346 54 33 21 Auxiliary Feedwater 607 15 15 1
1 of 3
Revised August 21, 1979 SURRY POWER STATION UNIT 1 TABLE 4-lB (cont'd)
PIPE SUPPORT STATUS
SUMMARY
OUTSIDE CONTAINMENT -
SHOCK 2 Modifica-System Total No.
No. Acceptable tions or and of (Evaluation No. Under Additions Prob. No Supports Complete)
Evaluation Required Comments Component Cooling 488/480 33 33 507/481 27 27 509A/D 32 32 509B 9
9 509C 13 13 512 9
9 517 38 38 526C 17 17 527A/C 18 18 612 20 20 614 19 19 766 18 18 1512 8
8 2526 20 20 2527/2529 23 23 Containment Vacuum CVl 3
3 1*
3" HP Steam 746 19 19 2 of 3
System and Prob. No Fire Pro-tection CFl CF2 Diesel Muffler 1040 Notes:
Total No.
of Supports 14 14 18 SURRY POWER STATION UNIT 1 TABLE 4-lB (cont'd)
PIPE SUPPORT STATUS
SUMMARY
OUTSIDE CONTAINMENT -
SHOCK 2 No. Acceptable (Evaluation No. Under Complete)
Evaluation 3
14 14 15 Modifica-tions or Additions Required 3*
Revised August 21, 1979 Comments The number in the "Modifications" or Additions" Column are already included in the status shown in the "Acceptable (Complete)" column.
The number in the "Total Supports" column equals the number in the "Acceptable" plus the number in the "Under Evaluation" column.
- These modifications are not included in Table 4-2 as they do not belong to systems LHSI, AFW, CRS and HHSI (outside the containment).
These modifications have been identified to field and will be completed before start up.
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Problem Support No.
No.
334B 465 508 508 508 525A 525A 525A 544 544 544B 548B 548B 548B
SUMMARY
Description of Modification or Overstressed Condition Modified Since August 1, 1979 Attributable Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS NOTED Snubber modification Support member overstressed Snubbers over allowable Snubbers over allowable Weld over allowable Prevents growth in one direction Add shock suppressor due to H-1 overstressed Support overstressed Overstressed with new loads Overstressed with new loads Weld over stress allowable No lateral restraint capability 6-way restraint not properly functioning 6-way restraint not properly functioning No lateral movement due to thermal and seismic U-bolts overstressed Yes. Note 1 No No No No No Yes. Note 2 Yes. Note 3 No No No No No Yes,_ Note 4 No No 1 of 6 Support Function As-built Seismic Reanalysis Seismic Reanalysis As-built As-built Seismic Reanalysis As-built As-built As-built As-built As-built As-built As-built As-built As-built Resolution Add horizontal shock suppressor.
Removed Support H-21.
Add horizontal snubber.
Add horizontal and vertical snubbe:rs, Modify support.
Modify support.
Add horizontal shock suppressor.
Modify support.
Redesigned and modified to VC-LC, Redesigned and modified to VC-LC, Support modified.
Redesigned and modified support to receive lateral load.
Redesigned (modified to ~-way restraint).
Redesigned (modified to 3-way restraint). Ganged with H72A Restore to original configuration.
Redesigned and modified support by adding bracing member.
SURRY POWER STATION, UNIT 1 TABLE 4-2 (Cont)
Modified Since Problem Support Description of Modification or Overstressed Condition August 1, 1979 Attributable No.
No.
Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS NOTED 548C 548C 555 555 555 555 546.t,560
. 546/560 546/560 Hl7A Hl7B Hl7C H75 HlO H28 H29 H30 H39A H39B PT-185 PT"-208 546/560 PT-130 546/560 *PT-216 Lugs overstressed on gang No hanger - anchor U-bolt subjected to lateral No loads over allowable loads Integral attachment No overstressed Horizontal and vertical No structural member restraining.
pipe movement Vertical member restraining No pipe motion Vertical member restraining No pipe motion Integral attachment over-No stressed for suppo~t H39A Added due to H39A No Added due to H39A No Added due to H39A No Added due to H39A No 546/560 PT-310 Added due to H39A
- No 546/560 H50*
Integral attachment over-Yes~ Note 2 stressed for support H50 562 H26 Modified due to H39B. Inte-No gral attachment overstressed for H39B.
562 H29A Modified due to H39B.
- Inte-No 2 of 6 As-built As'.""built Seismic Reanalysis Thermal movement Thermal moveme*nt Thermal movement As-built As-built As-built As-built As-built As-built As-built As-built As-built Revised August 21, 1979 Resolution Redesigned and modified by removing attachments to relieve pipe overstress conditions.
Replace U-bolt with framed member.
Add lateral shock suppress.or.
Rester~ to original intent.
Restore to original intent.
Restore to original intent.
Replace anchor by a 3-way restraint.
Add vertical shock suppressor to reduce *1oads.
Add lateral constrainto Add lateral constraint and.vertical A constraint.
W Add lateral constraint.
Add late~al consiriint.
Add North South East West restraint.
Modify support by adding U-bolt.
Modify 2-way support to
SURRY POWER STATION~ UNIT 1 TABLE 4-2 (Cont)
Modified Since Problem Support No.
No.
Description of Modification or Overstressed Condition August 1, 1979 Attributable Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS.NOTED 562 562 H29B gral attachment overstressed for H39B.
PT-265 Added due to H39B. Integral No attachment overstressed for H39B.
- PT~340 Modified due to H39B. Inte-No gral attachment overstressed for H39B.
562 H-39B Integral attachment over-Yes. Note 4 stressed
- 562 PT-183 Added due to H39B. To reduce No load on hanger H39B.
U-bolt modified to reduce loads on Hl7B Added to reduce anchot ioads No No.
546/5600 Hl5B.
546/5600 PT-155 546/5620 H-l.5A U-bolt modified to reduce loads on Hl 7 A-Yes. Note 2 546/5620 PT-230 Added to reduce anchor loads 636 708 708 708 H36 Plate overstreised *
- PT-1 Lateral load on U-bolt overstressed Hl27 Member overstressed PT-380 Lateral restraint over-stressed No No No No
.No 3 of 6-As-built As-built As-built As-built Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis Seismic Reanalysis As-built -
As-built As-built As-built Revised August 21, 1979 Resolution 3-way support.
Add lateral constraint. Reduce loads at anchor point.
Modify vertical constraint.
Replace anchor by a 3-way restraint.
Ganged with H39A, Add 2-way support.
Redesigned and modified ganghanger from 1-way CLC).
Add LC-VC to reduce loads at anchor.
Redesigned and modified ganghanger from 1-way CLC) to 2.-way CLC-VC).
Add LC-VC to reduce loads.
. Modify anchor by adding gusset.
Add lateral restraint.
Modify support to vertical and lateral constraint. *.
Modify support to vertical
- and lateral constraint.
Problem Support No.
No.
1525A 1525A 1525A 1525A 152.SA 1525A 1525A 1525A 603A PT-1000 PT-5000 PT-8000 PT-134 PT...;232 PT-314 PT-2510 PT-5802 3,
SURRY POWER STATION, UNIT 1 Description of Modification or Overstressed Condition TABLE 4-2 (Cont)
Modified Since August 1, 1979 Attributable Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS*NOTED Integral attachment CH-2>
overstressed Yes. Note 2 Seismic Reanalysis Delete due to H-2 No Seismic Reanalysis U-bolt and frame over-No
. Seismic stressed Reanalysis Added due to HlOA Yes. Note 2 Seismic Reanalysis Added due to H2 Yes. N.ote 2 Seismic Reanalysis Ad~ed due to HlOA 2
Seismic Yes. *Note Reanalysis Add due to HZ
- Yes. Note 2 Seismic.
Reanalysis Hanger overstres~ed.
. Yes. Note 1&3 Seismic Reanalysis Pipe straps overstre~sed No As-built 603A 603A 4
~ Pipe straps overstressed.
Yes. Note 2 As-Built 7
603A 5
603B.
13 Pipe straps overstressed Vertical restraint only re-quired, but support had zero lateral clearance.
Uplift restraint is re-quired, but support had negative vertical restraint only.
No
- As.:.built No.
As-built No
- As-built.
4 of 6 Revised August :1, 1979 Resolution Modify anchor to VC.to reduce anchor load.
Delete axial support and 1-way LC to reduce anchor load.
Modify frame.
Add LC to reduce anchor loads.
Add LC to reduce loads.
Add LC to reduce anchor loads.
Add LC to reduce loads.
Modify support.
Add gussets weld size.
to all and increase Add gusse.ts to all and increase*
weld size.
Add gussets weld size.
to all and increase Modify support to provide
- lateral clearance.
Modify support to provide uplift restraint.
SURRY POWER STATION, UNIT 1 TABLE 4-2 (Cont)
Modified Since Problem Support Description of Modification or Overstressed Condition August 1, 1979 Attributable No.
No.
Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS NOTED 6J3B 605B 605B 603A 605B 605A 605A 605A 605A 605A 605A 605A 607 731A 731A 10 4
6 Vertical support only re-quired, but support is a vertical restraint and lateral restraint.
Support members overstressed Pipe strap weld stress over allowable H-2 Lateral clearance insufficient H-2 Lateral clearance insufficient PT-13 Need vertical restraint PT-23 Need vertical and lateral restraint PT-28 Need vertical and lateral restraint PT-4295 Additional support PT-4300 Additional support 2020
- Delete lateral restraint 2005 Delete lateral restraint PT 77 U-Bolt overstressed SI-C-90 Support member overstressed PT 46 Integral attachment over-stressed No No Yes. Note 2 Yes. Note 2 No No Yes. Note 5 Yes Note 5 Yes. Note 5 Yes. Note 5 No. Note 7 No. Note 7 No. Note 6 No. Note 6 No. Note 6 5 of 6 As-built As-built As-built Thermal movement Thermal movement As-built As-built As-built As-built As-built As-Built As-Built As-Built Support Function Support Function Revised August 21, 1979 Resolution Remove top and side members of support.
Replace two W4xl3 members with TS4x4xl/2.
Add two gussets to reduce load at connection.
Modify restraint.
Modify restraint.
Modify vertical support.
Modify vertical support.
Modify vertical support.
Add new support.
Add new support.
Modify support.
Modify support.
Delete U-Bolt Add structural brace.
Add N-S restraint.
Gang Hanger Problem #731B Point #44.
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Ii SURRY POWER STATION, UNIT 1 TABLE 4-2 (Cont)
Description of Modified Since Problem Support Modification or No.
No.
Overstressed Condition August 1, 1979 Attributable Submittal To:
INSIDE REACTOR CONTAINMENT UNLESS NOTED 731B SI-C-91 Support member overs~ressed No. Note 6 Support Function 745 731A 731B 735 735 735 NOTES:
PT 45 PT 38 PT 36 PT 20 PT 35 PT 50 Support overstressed Support overstressed Support overstressed Support overstressed Support overstressed Support overstressed
- 1.
Revised Point No.
- 2.
Deleted due to more detailed analysis.
- 3.
Modified due to more detailed analysis.
No. Note 6 No. Note 6 No. Note 6 No. Note 6 No. Note 6 No. Note 6 As-Built Support Function Support Function As-Built As-Built As-Built Revised August 21, 1979 Resolution Add structural brace.
Modify support.
Modify support.
Modify support.
Modify support.
Modify support.
Modify support.
- 4.
Deleted since this support is ganged with other support and they shall be considered as one support.
- 5.
Deleted since this change is due to stress.
- 6.
Modification outside containment.
Added to Table 4-2 as required by the SER.
- 7.
Modification added - Non-Functional Structure to be removed.
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