ML18046A890

Forwards Evaluation for SEP Topic III-5.B, Effects of Pipe Breaks on Sys,Structures & Components Outside Containment. Evaluation Based Primarily on Work Performed Between 1973 & 1975 & Documented in Encl Bechtel Associates Rept 6

ML18046A890
Person / Time
Site:	Palisades
Issue date:	08/25/1981
From:	Vincent R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML18046A891	List: ML18046A890 ML18046A892
References
TASK-03-05.B, TASK-3-5.B, TASK-RR NUDOCS 8109010337
Download: ML18046A890 (14)

Text

/

consumers Power company*

General Offices: 212 West Michigan Avenue, Jackson, Ml 49201 * (5171 788-0550 August 25, 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 U S Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC III-5.B, EFFECTS OF PIPE BREAKS ON SYSTEMS, STRUCTURES AND COMPONENTS OUTSIDE CONTAINMENT Attached is the Consumers Power Company evaluation for SEP Topic III~5.B for the Palisades Plant.

This evaluation is based primarily on work performed between approximately 1973 and 1975 and. documented in Bechtel' Associates Professional Corporation Special Report No 6 for the Palisades Plant.

Revision 2 of this report was submitted to the NRC in our letter of July 27, 1973.

The report and CPCo actions taken in response to this issue were found acceptable by the NRC in a letter dated August 7, 1973.

Since that time a final revision has been made to the report, but not docketed.

Included with this letter, therefore, is Special Report No 6, Revision 3, dated June 30, 1975.

Robert A Vincent Staff Licensing Engineer CC Director, Region III,. USNRC NRC Resident Inspector - Palisades RAV 81-23

~---1

( ~/,~9010337 8,10825~

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PALISADES PLANT SEP TOPIC III-5.B HIGH ENERGY LINE BREAK OUTSIDE CONTAINMENT I.

INTRODUCTION The safety objective of Systematic Evaluation Program (SEP) Topic III-5.B, "Pipe Break Outside Containment," is to ensure that pipe breaks would not caU:Se the loss of needed functions of safety-related systems, structures, and components and to ensure that the plant can be safely shut down in the event of such breaks.

The needed functions of safety-related systems are those functions required to mitigate the effects of the pipe break and safely shut down the reactor plant.

High energy line break (HELB) analysis for piping systems outside contain-ment at the Palisades nuclear plant was furnished in Special Report-6 (SR-6),

"Analysis of Postulated High Energy Line Break Outside Containment," Rev. 3, dated June 30, 1975.

The high energy lines were identified therein, and the postulated breaks were assumed based on the mechanistic.approach outlined in Standard Review Plans (SRPs) 3.6.1, 3.6.2 and their attached Branch Tech-nical_ Positions (BTPs) APCSB 3-1 and MEB 3-1, dated November 24, *1975.

Sub-sequent to the 1975 HELB analysis report, all safety piping outside containment of the Palisades nuclear plant was reanalyzed and modifications (mainly to pipe supports) were made from 1979 through 1981.

This evaluation includes the following:

a.

A review of the analytical results recorded in SR-6.

b.

A comparison of the criteria used in SR-6 with current HEL:B criteria.

c.

The effect of reanalysis on break points selected by the mechanistic stress criteria and an evaluation of break points determined by stresses if the break points differ from SR-6.

II.

CURRENT.REVIEW CRITERIA

a.

US NRC, SRP 3. 6.1 and 3.6. 2 and their companion BTPs, APCSB 3-1 and MEB 3-1, dated November 24, 1975.

III.

RELATED SAFETY TOPICS AND INTERFACES

a.

SEP Topic III-4C, "Internally Gerierated Missiles (Outside Containment)"

• b.

SEP Topic III-12, "Environmental Qualification of Safety-Related Equipment

c.

Palisades FSAR Volume III, Appendix A, (revised October 24, 1980) *

• d. *Palisades Plant Special Report-6, "Analysis of Postulated High Energy Line Break Outside Containment," Rev. 3, June 30, 1975.

e.

NRC IE Bulletin 79-14.

SEP TOPIC III~5.B 2

_ _!~-- - _Jl!lffi!:!.~_ 9.737 IV.

EVALUATION

a.

Analytical results recorded in SR-6.

The criteria used in SR-6 is given on page 1-2 of the report.

Based on the criteria, the report defines safety systems:(see page 5-1) and evaluates the results of high energy line breaks outside containment with respect to plant safety.

The report (page 9-1) concluded that modifications to the plant were desirable, and these modifications

_were incorporated in* the 1975 time frame.

In addition a program was initiated for augmented ISI of selected lines for which modifications were impractical.

In general, the safety equipment required. for -safe shutdown listed by

. SR-6 (table 4-1) is still valid, ie, no significant modifications_ have.

been made to the plant in this area since 1975.

Also, the lines-eval-uated in SR-6 appears.valid for the criteria used at the time.

b.

Criteria A review of the criteria used in SR-6 versus the criteria given by SRP 3.6.1 shows that the criteria used by sR..:.6 is the same as current criteria except as follows:

i.

SR-6 (page 1-2) considered that temperature must exceed 200°F and pressure must exceed 275 psig if a line is to be classified as--

high energy.

SRP 3.6.1 defines a line as high energy if either the pressure..£!:. the temperature values are exceeded.

Tw_o systems*

which were excluded from consideration by the earlier criteria would now be considered as high energy systems by current criter-ia.

These systems include the reactor coolant let _down piping (see page 6-3 of SR-6) and the. heating steam* and. condensate sys-tem.

With*respect to the let down piping, the effects of a break in this 2" line would not be considered significant 'Un.de:r the size and/or location criteria as discussed on page 7-1 of SR-6.

With respect to the heating steam system, a discussion of-pipe break effects is provided as Attachment I. In general, the energy contained within this system is insufficient to produce unacceptable consequences.

ii. Brea.ks *in portiOns oT'the auX:i.Iiary* feedwater system were* deemed -

not-credible because of low usage (see page. 7.. 3 of.SR~6) whereas

• footnote 6, page 14 of SRP 3. 6. 2 specifically notes that the aux-iliary feedwater system is a high energy system.

Significant.

modifications are being made to the system in response to NUREG 0737 commitments.

HELB cqnsiderations for this system arebeirig addressed as part of the system design.

SEP TOPIC III-5.B 3

-- -- --iii _: _____ Bre:ak.s selected on stress points.

Certain.high energy line breaks were postulated by SR-6 based on calculated stresses.

Breaks were assumed in a pipe run at two intermediate locations of highest combined stresses.

Breaks were also assiimed when calculated stresses exceeded 0.8 (Sh + SA) or the expansion stresses exceeded 0.8 SA.

Subsequent to comple-tion of SR-6, large bore safety piping at Palisades was re-analyzed based on "as-built" data collected in 1978 and 1980.

As a result of this reanalysis, some points of highest combined stresses changed from those points considered by SR-6.

The high stress point relocations have been reviewed on a sample basis.

The relocations are small and are not significant with respect t.o installed restraints, ie, the relocations do not invalidate SR-6 results.

SR-6 postulated no breaks based on the 0.8 (Sh + SA) or 0.8 SA criteria (see tables 7-1, 7-2 and 7-3 of SR-6).

While the re-analysis performed in the 1979-1981 period resulted in changes to the calculated pipe stress values, none exceeded the criteria except for point 9 of the main steam dump line.

Since calculated stresses exceed 0.8 (Sh+ SA) by only 2.3%; this value can be neglected.

See attached tables 1; 2 and 3 for recalculated stress

• values which may be compared with those of SR-6. *.

V.

CONCLUSION*.

Based_ on the evaluation performed per SR-6 and the above di~cussions, reasonable certainty exists that the Palisades plant I!leets the intent of SRP 3.6.1 and SRP 3.6.2, with the single exception of auxiliary feed--

water system which is being modified per NUREG 0737.

Since these modi-fications include.HELE considerations; no additional actions are required with respect to SEP Topic III-5.B.

(

• TAllLE l CONSUMERS POWER COMPANY.

PALISADES NUCLEAR PLANT;.

I HIGll ENERGY PIPE FAILURES OUTSIDE CONTAINMENT -

SUMMARY

OF O~ERATING STRESSES (Calculated 1979-1981)

• System:

HAIN STEAM (EB-l-36", EB-l-26")

Point Press!' re Weight sh (l)

Seismic l.2Sh (2)

ExpAnsion SA (3) 0.8(Sh+SA) (4)

No.

Stress 1 p Stress 1 w p + w Stress 1 S r+w+s Stress 1 T P+w+S+T l

6,459 1,325 7,784 17,500 6,660 14,444 21,000 2,994 26,250 17,438 35,000 2*

6,459.

3,399 9,858 17,500 3,913

13. 771 21,000 6,115 26,250 19,886 35,000 3

6,4,59 2,992 9,451 17,500 3,865 13,316 21,000 5,336 26,250 18,652 35,000 4

6,459 748 7,207 17,500 3,873 11,080 21,000 3,782 26,250 14,862 35,000 5

6,459 875 7,334 17,500 3,479 10,813 21,000.

4,592 26,250 15,405 35,000 6

6,459 1,099 7,558 17,500 3,425 10,983 21,000 2,876 26,250 13,859 35,000 e

7 8,210 l, 111 9,321 17,5,00 7,261 16,582 21,000 5,903 26,250 22,485 35,000 8

8,210 1,089 9,299 17,500 5,785 15,084 21,000 7,519 26,250 22,063 35,000 9

8,210 321 8,531 17,500 5,831 14,362 21,000 6,754 26,250 21,116 35,000 10 a.no 321 8,531 17,500 5,831 14,362 21,000 6,754 26,250 2 l, 116 35,000 11 8,210 228 8,438 17,500 5,313 13,751 21,000 5,975 26,250 19,726 35,000 12 8,210 1,459 9,669 17,500 5,320 14,989 21,000 6,026 26,250 21,015 35,000 13 8,210 2,557 10,767 17,500 5,481 16,248 21,000 7,084 26,250 23,332 35,000 14 8,2,10 3,372 11 ;5a2 17,500 7,353 lR,935 21,000 7,590 26,250 26,525 35,000 15 8,HO 3,459 11,669 17,500 9,872 21,541 21,000 9,901 26,250 31,442 35,000 16 5,457 1,016 6,473 17,500 3,372 9,845 21,000 3,450 26,250 13,295 35,000 17 8,210 l,717 9,927 17,!100 10,4 79 20,li06 21,000 7,091

. 26,250 27,497 H,000 18 8,210 941 9,151 17,500 9,567

18. 718 21,000 6,602 26,250 25,320

• j5,ooo 19 8,210 2,253 10,463

17. 500 5,655 16, 118 21,000 4,509 26,250 20,627 35,000 20 8,210 3,243 11,453 17,500 5,224 16,677 21,000 3,812 26,250 20,489 35,000.

21 a,no 2,973 ll, 183 17,500 6,520 17,703 21,000 7,886 26,250 25,589 35,000 22 8,210 2,949 ll, 159 17,500.

9,429

. 20,588 21,000 11,016 26,250 31,604 35,000 23 5,4157 912 6,369 17,500 3,333 9,702 21,000 3,600 26,250 13,302 35,000 24 6,459 1,981 8,440 17,500 3,326 11,766 21,000.

2,546 26,250

14. 312 35,000 25 6,4'59 4,532 10,991

17. 500 3,509 i4,500 21,000.

4,941 26,250 19,441 35,000 26 6,4.59 4,872 ll,331 17,500 4,020 15,351 21,000 5,561 26,250 20,912 35,000 27 6,4.59 1,049 7,508

• 17,500 3, 341, 10,852 21,000 4,0117 26,250 14,899 35,000 28 6,459 1,007 7,466

,17,500 3, 795 11, 261 21,000

. 3,458 26,250 14,719 35,000 e

29 6,4*59 883 7,342 17,500 2,309 9,651 21,000 l, 133 26,250 10,784 35,000 30 8,212 911 9,123 17,500 4,4.4i 13,564 21,000 6,266 26,250 19,830 35,000 31 8,2*12 424 8,636 17,500 4,539 13,175 21,000 7,005' 26,250 20, 180 35,000 32 8,2.12 424 8,636 17,500 4,539 13,175 21,000 7,005 26,250 20, 180 35,000 33 8,212 865 9,077.

17,500 4, 108 i'3, 185 21,000 6,291 26,250 19,4 76 35,000 34 8,i12 1,591 9,803 17,500 4,641 14,444 21,000 6,807 26,250 21,251 35,000 35 e.2.12 1,288 9;500 17,500 3,843 13,343 21,000

. 5,822 26,250 19,165 35,000 Page l of 2

TABLF. 1 (Continued)

.HIGH ENF.RGY,PIPE FAILURES OUTSIDE CONTAINMENT -

SUMMARY

OF OPERATING STRESSES (Calculated 197.9-1981)

System:

Point No.

36 37 38 39 40 41 42 43 44 45 46 47 HAIN.STEAM (E8-l-36M, EB-1-26")

Pressure Weight sh (1)

Seismic Stress 1 p Stress 1 w*

p +: w Stress 1 s P+W+S 8,212

' 1, 519 9,731 17,5.00 5,881 15,612 11,212 2,472 lff, 684 17,500 6,373 17,057 5,,457 2,432 7,889 17,500 '

8,292 16,181 5;457

'1,041 6,498 17,500

.4,305 10,803 8,,212 1,124 9,336 17,500 7,476 16,812 8,212 623 8,835 l-7' 500 '

6,816 15,651 8,212 2,765 10,977 17,500 4,968 15,945 8,212 2;321 10,533 17,500 3,995 14,528 8,212 809 9,021 17,500 3,299 12,320 8,212 1,476 9,688 17,500 4,605 14,293 5,457 3,223 U,435 17,500 8, 136 24,212 5,457 1,469 9,~81 17,500 3,982 13,663 NOTES:

1.* Sh* Allowable Limit of P + W per Applicable Code

2.

• l.2Sh *Allowable Limit of P + W + S per Applicable Code

3.

SA *Allowable Limit of T per Applicable Code 1.2Sh (2)

Expansion Stress 1 T 21_,000 2,325 21,000 4,403 21,000 8, 548 21,000 4,320 21,000 4,519 21,000, 3,976 21,000 1,736 21,000 1,621 21,000 2,609 21,000 3,899 21,000 5,555 21,000 2,687 4;

0.8(Sh + SA)

• Threehold of Stress for Hnnd.atory Drenk Location in thin Study, AEC SA (3) 26,250 26,250 26,250 26,250 26,250 26,250 26,250 26,250 26,250 26,250 26,250 26,250 I:

I CONSUMERS POWER COMPANY PALISADES I

NUCLEAR PLANT l

P+W+S+T 0.8(Sh+SA) <v 17,937 35,000 21,460 35,ooo 24,729 35,000 15,123 35,000 21,Hl 35,000 19,627 35,000 17,681 35,000 9'

16,149 35,000 14,929 35,000 18,l'J2 35,000 29,767 35,000 16,350 35,000 Page 2 of 2

I TABLE 2 CONSUMERS POWER COMPANY PALISADES PLANT HIGH ENERGY PIPE FAILURES OUTSIDE CONTAINMENT -

SUMMARY

OF OPERATING STRESSES (Calculated 1979-1981)

System:

FEEDWATER (DB-1-18" & EB-9-18", DB-1-12")

POINT PRESSURE WElGllT sh (I)

SEISMIC l.2Sh( 2).. EXPANSION SA (3) 0.8(Sh+SA) (4)

NO.

STRESS, P STRESS, W p + w STRESS, S P+w+S STRESS 1 T P+w+S+T l

5,787 247 6,034 15,000 3, 194 9,228 18,000 6,123 22,500 15,351 30,000 9'

2 5,787 125 5,912 15,000 710 6,622 18,000 801 22,500 7,423 30,000 3

5,787 250 6,037 15,000 172 6,209 18,000 493 22,500 6,702 30,000 4

5,787 280 6,067 15,000 2,215 8,282 18,000 l0,523 22,500 18,805 30,000 5

5,787 769 6,556 15,000.

2,585

9. 141 18,000 10,893 22,500 20,034 J0,000 6

5,787 516 6,303 15,000 1,800 8, 103 18,000 10,191 22,500 18,294 J0,000 7

5,787 7.40 6,527 15,000 1,533 8,060 18,000 8,385 22,500 16,445 30,000 8

5,787 571 6,358 15,000 1,648 8,006 18,000 4, 182 22,500

12. 188 30,000 9

5,787 337 6,124 15,000 2,072 8, 196.

18,000 3,123 22,500 I 1, JI 9 30,000 10 5,787 273 6,060 15,ooo*

2*, 171 8,231 18,000 4,060 22,500 12,291 J0,000 I I 5,787 25 5,812 15,000 1, 937

7. 749 18,000 2, 733 22,500 10,482 30,000 12 5,787 567 6,354 15,000 1,924 8,278 18,000 1,508 22,500 9,786 30,000 13 5,787 1,065 6,852 15,000 3,683 10,535 18,000 6,841 22,500 17,376 30,000 14 5,787 745 6,532 15,000 2,907 9,439 18,000 5, 112 22,500 14,551 30,000 15 16 5,787 377 6,164 15,000 1,844 8,008 18,000 3,222 22,500

).),230 30,000 p

5,896 903 6,690 15,000 2,011 8,701 18,000 2,604 22,500 I I,305 30,000 18 5,896 1,009 6,905 15,000 3,423 10,328 18,000 2, 154 22,500 12,482 30,000 19 5,896 302 6, 198 15,000 1,115 7,313 18;000 641 22,500 7,954 30,000 20 5,896 218 6, 114 15,000 1,013 7, 127 18,000 856 22,500 7,983 30,000 21 5,787 773 6,560 15,000 3,255 9,815 18,000 842 22,500 10,657 30,000 22 5,787 632 6,419 15,000 2,278 8,697 18,000 2,323 22,500 I I,020 30,000 23 5,787 387 6,174 15,000 3,880 10,054 18,000 3,950 22,500 14,004 J0,000 24 5,787 126 5,913 15,000 1,897 7,810 18,000 1,682 22,500 9,492 30,000 25 5,991 487 6,478 15,000 3,512 9,99.0 18,000 2,516 22,500 12,506 J0,000 26 5,991 345 6,336 1'5,000 1, 713 8,049 18,000 806 22,500 8,855 30,000 27 5,787 1, 395 7, 182 15,000 5, 165 12,347 18,000 4,477 22,500 16,824 30,000 28 5,787 1,459 7,246 15,000 3,960 11,206 18,000 3,272 22,500 14,478 30,000 29 5,787 l, 375 7, 162 15,000 l,828 10,990 18,000 2,651 22,500 13,641 30,000 30 5,787 1,056 6,843 15,000 3,892 10,735 18,000 2, 114 22,500 12,849 J0,000 30A 5,787 I,087 6,874 15,000 l,490 8,364 18,000 l,364 22,500 9,728 30,000 31 5,787 I, 167 6,954 15,000 3,208 I0, 162 18,000 3,952 22,500 14,114 30,000 Page l of 4

TABLE 2 (Continued)

CONSUMERS POWER COMPANY PALISADES PLANT H IGll ENERGY PIPE FAILURES OUTSIDE CONTAINMENT -

SUMMARY

OF OPERATING STRESSES

(~alculated 1979-1981)

System:

FEEDWATER (DB-1-18" & EB-9-18", DB-1-12 )

POINT PRESSURE WEIGllT

. sh (1)

SEISMIC l.2Sh( 2)

EXPANSION SA (3) 0.8(Sh+SA) (4)

NO.

STRESS, p STRESS, W p + w STRESS, S P+w+S STRESS 1 T P+w+S+T 32 5,787 808 6,59S 15,000 3, 195 9,790 18,000; 4,756 22,500 14,546 30,000 32A 5,787 759 6,546 15,000 3,893 10,439 18,000' 4,900 22,500 15,339 30,000 33 5,787 644 6,431 15,000 4,465 10,896 18,000.

5,783 22,500 16,679 30,000 34 5,787 557 6,344 15,000 4,720 11;064 18,000 4,995 22,500 16,059 30,000 e*

34A 5,787 l, 132 6,919 15,000 6,663 13,582 18,000 6,399 22,500 19,981 30,000 35 5,787 2,401 8,188 15*,000 7,345 15,533 18,000 7,898 22,500 23,431 30,000 36

4. 587 490 5,077 15,000 1,635

• 6, 712 18,000 1,458 22,500 8, 170 30,000 37 4,587 855 5,442 15,000 3,660 9, 102 18,000 2,679 22,500

11. 781 30,000 38 5,680 1,128 6,808 15,000 3,695 10,503 18,000 3,695 22,500 14,198 30,000 39 5,680 l, 170 6,850 15,000 4,244 I 1,094 18,000 5,916 22,500 17,010 30,000 40 5,680 3,843 9,523 15,000 8, 123 17,646 18,000 10,622 22,500 28,268 30,000 41 4;587 858 5,445 15,000 2,616 8,061 18,000 4, 114 22,500 12,175 30,000 42 4,587 632 5,219 15,000 3,468 8,687 18,000 4,325 22,500 13,012 30,000 43 4,587 613 5,200 15,000 3,603 8,803 18,000 4,317 22,500 13, 120.

J0,000 44 4,587

)91 4,978 15;000 1, 942 6,920 18,000 2,264 22,500 9, IUl1 J0,000 45 4,587 69 11,656 15,000 3,812 8,'168 lR,000 5,780 22,500 14,248 30,000 46 5,699

1. 382 7,081 15,000 10,205 17,286 18,000 10,760 22,500 28,046 30,000 47 5,680 888 6,568 15,000 5, 104 11,672 18,000 2,961 22,500 14,6)3 J0,000 48 5,680 768 6,448 15,.000 4, 187 10,635 18,000 2,018 22,500 12,653 J0,000 49 5,680 185 6,465 15,000 5,393 11, 858.

18,000 2,376 22,500 14,234 30,000 50 5,680 509 6, 189 15,000 5,396 11,585 18,000

.2,861 22,500 14,446 J0,000 51 5,680 220 5,900 15,000 4,398 10,289 18,000

2. 712 22,500

13. 001 30,000 52 5,680 195 6,475 15,000 5,074

11. 549 18,000 1,037 22,500 12,586 30,000 53 5,680 188 5,868 15,ooo.

6, 155 12,023 18,000 1,695 22,500 13, 718 30,000 54 5,680 196 5,876 15,000 6,872 12; 748 18,000 1,224 2,2,500 lJ. 972 30,000 55 5,680*

140 5;020 1$,000 6,380 12,200 18,000 337 22,500 12,537 30,000 56 5,680 212 5,892 15,000 9;705 15,597.

18,000 3,310 22,500 18,907 30,000 5}

5,680 401 6,081 15,000 9,248 15,329 18,000 3,919 22,500 19,248 30,000 58 5,680 549 6,229

• 15,000 4,916 11,145 18,000 3,503 22,500 14,648 30,000 59 5,680 509 6, 189 15,000 9,023 15,212 18,000 2,723 22,500 17,935 30,000 60 5,680 348 6;028 15,000 6,801 12,829 18,000 3,815 22,500 16,644 30,000 Page 2 of 4

TABLE 2 (Continued)

CONSUMERS POWER COMPANY PALISADES PLANT llIGll ENERGY. PIPE FAIWRES OUTSIDE CONTAINHENT -

SUMMARY

OF OPERATING STRESSES (Calculated 1979-1981)

System:

FEEDWATER (DB-1-18"' & EB-9-18"', DB-1-12")

• POINT PRESSURE WEIGllT sh (I)

SEISMIC l.2Sh( 2)

EXPANSION (3) 0.8(Sh+SA) (4)

NO.

STRESS 1 p STRESS, W p + w STRESS, S P+w+S STRESS 1 T SA P+w+S+T 61 5,680 2 71 5,951 15,000 7,357 IJ,308 18,000 4,333 22,500 17,641 30,000 62 e

63 5,680 472 6, 152 15,000 8,015 14,167

.18,000 6,236 22,500 20,403 30,000 64 5,680 162 5,042 15,000 4,259 10, 101 18,000 3,078 22,500 13, l 79 30,000 65.

4,587 124 4, 711 15,000 l, 119 5,830 18,000 1,218 22,500 7,048 30,000 66 4,587 268 4,855 15,000 3, 949 8,804 18,000 l, 967 22,500 10,771 30,000 67 5,699 l,475 7, l 74 15,000.

8,302 15,476 18,000 4,386 22,500 19,862 30,000 68 5,680 538 6,218 15,000 3, 774 9,992 18,000 3,947 22,500 13, 939 30,000 69 5,680 333 6,013 15,000 l,865 7,878 18,000 2,020 22,500 9,898 30,000 70 5,680 332 6,012 15,000 1,765

7. 777 18,000 1,516 22,500 9,293 30,000 71 4,587 2,077 6,664 15,000 5,363 12,02 7 18,000 2, 171 22,500 14,198 30,000 72 4,587 683 5,270 15,000.

930 6,200 18,000 679 22,500 6,879 30,000 7J 5,787 441 6,228 15,000 147 6,375 18,000 535 22,500 6,910 30,000 74 5,787 1, 293 7,080 15,000 5, I 11 12,191 18,000 4,914 22,500 17, 105 30,000 75 5,787 l, 103 6,890 15,000 5,624

12. 514 18,000 5,308 22,500 17,822 J0,000 76 5,787

)99 6, 186 15,000 J,012 9,1911 18,000 3,525 22,500 12,723 30,000 77 5,787 665 6,452 15,000 J,Otd 9,493

.18,000 4,577 22,500 14,070 30,000 78 5,787 620 6,407 15,000 2,840 9,247 18,000 4,693 22,500

13. 940 J0,000 79 5,787 663 6,450 15,000 2, 191 8,641 18,000 J,845 22,500 12,486 30,000 80 5,787 341 6, 128 15,ocio 1,860 7,988 18,000

. 319 22,500 8,307 30,000 81 5, 787 310 6,097 15,000 1,500 7,597 18,000 336 22, 5*00 7,933 30,000 82 5, 787 626 6,413 15,000 1,209 7,622 18,000 1,110 22,500 8,732 30,000 83 5,787 1,700 7,487 15,000 5,035 12,522 18,000 4,280 22,500 16,802 30,000 83A 5,787

2. 364 8,151 15,000 6,817.

14,968 18,000 5, 54) 22,500 20,511 30,000 84

5. 787 2,467 8,254 15,000 7,077

15. 331 18,000 4,876 22,500 20,207 30,000 85

. 5. 991 l,056 12,404 15,000 3~321 15, 725 18,000 1,363 22,500 17,088.

30,000 86 5,991 804 6,795 15,000 2,212 9,007 18,000 952 22,500 9,959.

30,000 87 5,896 453 6, 349 15,000 1,010 7,359 18,000 1,047 22,500 8,406 30,000 88 5,896

)34 6,230 15,000 523 6,75) 18,000 474 22,500 7,227 J0,000 89 5,896 1,497 7,393 15,000 4, 707 12,100 18,000 1, 734 22,500 13,834 30,000 Page 3 of 4

TABLE 2 (Continued)

HIGH ENERGY PIPE FAILURES OUTSIDE CONTAINHENT -

SUHHARY OF OPERATING STRESSES (Calculated System:

POINT NO.

90 91 92 93 94 95 96 97 98 99 100 IOI 102 103 I 04 105 106 107 108 109 110 FEEDWATER (DB-1-18" & EB-9-18, DB-1-12")

PRESSURE WEIGllT sh (1)

SEISMIC STRESS,. P STRESS, W p + w STRESS, S P+w+S 5,8%

1,077 6,973 15,000 4, 720 11,693 5,787 900 6,687 15,000 4, I29 10,816 5,787 1,724 7,511 15,000 3,523 II,034.

5,787 1,784 7,571 I5,000 2,593 10, 164 5,787 1,801 7,588 15,000 2,950 10;538 5,787 2,467 8,254 15,000 2,935 ll, 189 5,787 759 6,546 15,000 2,429 8,975

5. 787 I, 365 7, 152 15,000 2,515 9,667 5,787 1,431 7,218 15,000 2,585 9,803 5,787 1,081 6,868

. 15,000 2,955 9,823 4,475 576 5,051 15,000 1,188 6,239 4,475 734 5,209 15,000 7,007 12,216 5,787 I, 393 7, 180 15,000

2. 728 9,908 5,787 1,4.25 7,212 15,000 2,083 9,295

5. 787 I, 275 7,062 15,000 2,171 9,233 5,787 I, 155 6,942 15,000 2, 176 9, 118 5,787 1,996

7. 783 15,000 2,873 10,656 5,787 362 6, 149 15,000 942 7,091

5. 787.

825 6,612 15,000 8,121 14,733 5,787 82 5 6,612 15,000 8, 121 14;733 5,787 283 6,070 15,000 4,924 10,994 NOTES*:

I.

Sh * *Allowable Limit of I' + W -per Applicable Code

2.

l.2Sh a Allowable Limit of P + W + S per Applicable Code J,

SA

• Allowable Limit of T per Appli~able Code 1,2Sh(2)

EXPANSION STRESS 1 T 1_8,000 2,819 I8,000 5, 967 18,000 6,410 i8,ooo 2,988 18,000 2,387 18,000 6,255 18,000 8,353 18,000 7, 197 18,000 6,398 18,000 5,212 18,0_00 1,430 18,000 8,434 18,000 2,056 18,000 1,786 18,000 835 18,000 1, 116 18,000 1,465 18,000 402 18,000 2,597 18,000 2 *. 597 18,000 1,342 CONSUHF.RS POWER COMPANY PALISADES PLANT 1979-1901)

SA (3) 0.8(Sh+SA) (4)

P+w+S+T 22,500 14,512 30,000 22,500 16,783 30,000 22,500 17,444 30,000 22,500 13, 152 30,000 22,500 12,925 30,000 22,500 17,4411 30,000 22,500 17,328 30,000 22,500 16,864 30,000 22,500 16,201 30,000 22,500 15,035 30,000 22,500 7,669 30,000 22,500 20,650 30,000 22,500 11, 964 30,000 22,500 11,081 30,000 22,500 10,068 30,000 22,500 10,234 30,000 22,500 12, 121 30,000 22,500 7,493 30,000 22,500 17,J30 30,000 22,500

17. 330 30,QOO 22,500 12,336 30,000

4.

0.8(Sh +SA)* Thres~old of Stress for.Mandatory Break Location in this study, AEC Page 4 of 4

)

TAIJl.I': 3 CONSUMERS POWER COMPANY PALISADES PLANT lllGll ENERGY PIPE FAILURES OUTSIDE CONTAINMENT -

SUMMARY

OF OPERATING STRESSES (Calculated 1979-1981)

System:

HAIN STEAM DUMP (EB-1-8", GB-19-8").

POINT PRESSURE WEICHT sh (I)

SEISMIC l.2S 11

( 2)

EXPANSION (3)

0. 8(Sh +SA) (4)

NO.

STRESS, p STRESS, w p + w STRESS, S P+w+S STRESS,. T SA P+w+S+T I

2,680 9

2,689 15,000 1,639 4,328 18,000 833 22,500 5, 161 30,000 2

2,680 927 3,607 15,000 2, 110 5, 717 18,000 l, l 30 22,500 6,847 30,000

3.

5,956 225 6, 181 15,000 1,091 7,272

. 18,000 2,610 22,500 9,882 30,000 4

5,956 l, 577 7,533 15,000 2,377 "9,910 18,000 5,397 22,500 15,307 30,000 5

5,956 932 6,888 15,000 l, 113 8,001 18,000 15,565 22,500 23,566 30,000 6

5,956 1,204 7, 160 15,000 1,159 8,319 18,000 15,559 22,500 23,878 30,000 7

5,956 I, 705 7,661 15,ooo*

1,679 9,340 18,000 9,157 22,500 18,497 30,000 8

5,956 1,868 7,824 15,000 I, 784 18,322 18,000 9,687 22,500 28,009 3_0,000 9

5,956 1,857 7,813 15,000 1,848 17,261 18,000

13. 441 22,500 30,702 30,000 NOTES:

I) Sh* Allowable limit of Pi~ per Applicable Code

2) l.2Sh

• Allowable limit of P+w+S per Applicable Code

3)

SA

• Allowable limit of T per Applicable Code

4) 0.8(Sh+SA)

• Threshold of Stress for Mandatory Brenk Location in this Study, AEC Criteria Page 1 of 1

ATTACHMENT I.

HIGH ENERGY LINE BREAK EVALUATION PLANT HEATING SYSTEM Steam from the heating boiler (M-8), and steam extracted from the LP turbine provide plant heating to auxiliary building, turbine building, reactor build-ing as well as process heat to the heat exchangers of safety injection and recirculating water (SIRW) tank, condensate tank, primary makeup tank, and domestic water tank (Figure 1).

The plant heating system is designed for the maximum service conditions of steam at 15 psig and 250°F.

The system meets the criteria defined in APCSB 3-1 of SRP 3, 6.1, for high energy fluid system.

The safety evaluation of high energy line breaks (HELB) pertaining to the system, as discussed herein, is based on the mechanistic approach outlined in SRP 3.6.2 and BTP MEB 3-1, dated November 24, 1975.

Branch 1, (JB-11-10") from the heating boiler (M-8), supplies heating steam to the following auxiliary facilities and areas located in the auxiliary building:

1.

• New and spent fuel handling, storage and shipment areas

2.

3.

4.

5.

6.

7.

Control room Radwaste, chemical and volume control e~uipment Emergency diesel generators and related auxiliary areas Safety injeetion system Containment spray system Component cooling system Branch 1 (JB:..ll-10"), in part, and branch 2 (JB-11-8") *from the heating boiler (M-8), in conjunction with steam extracted from the LP turbine provide plant heating steam to the following areas located in the turbine building.

1.. Turbine building auxiliary feed pump room

2.

Containment electrical penetration area

3.

Service water pump area

4.

Diesel fire pump area These auxiliary facilities housed in the auxiliary building and the turbine building are located within reinforced concrete enclosures, designed and constructed to Seismic Class 1 Standards.

The low pressure heating steam lines are physically separated from other safety-related structures, systems, and components in the auxiliary building and the turbine building.

The pip-ing is designed and fabricated in accordance with USAS B3Ll.0, 1967.

Any break along the high energy plant heating lines will not produce adverse environmental conditim in-the auxiliary faciliti~s *areas*;

Compartment pres-*

surization due to anticipated breaks will be ir+significant.

Jet impingement reactions on the struc.tures' systems and components in the vicinity are avoided by their physical separation from the plant heating steam lines.

Fluid thrust due to a broken line is insignificant because of low enthalpy of the fluid in the piping, and it does not affect the safety function of any critical system components.

Portions of the plant heating lines pass through the main steam*penetration room and main feedwater pene-tration room enclosed.in a section of the auxiliary building.

Main steam

.~

ATTACHMENT I 2

---~lines and main feedwater lines are restrained by structural steel whipping frames and concrete enclosures and low pressure plant heating steam line breaks have no affect on their functional integrity.

Also, due to the low fluid enthalpy a low pressure plant heating steam line break will not create pipe whipping.

The energy release due to full circumferential break of branch 1 (JB-11-10"),

providing heating steam to auxiliary building heating.units, part of turbine building heating units, and process steam to SIRW tank will be 877 BTU/sec.

Similarly, the energy release due to a full circumferential break of branch 2 (JB-11-8") of the heating boiler line, which supplies heating steam conjointly with steam extracted from the LP turbine to heating units in.the turbine build-ing, and process steam to the condensate heat exchanger, primary makeup system heat exchanger and domestic water heat exchanger, will be 832 BTU/ sec.

These energy releases will be dispersed through relatively large volumes within the auxiliary building and turbine building, respectively, creating no consequential adverse environmental effect on the safety-related structures, systems and components.

It is concluded that the low pressure plant heating steam line break outside containment will not hamper the normal plant operation~

1-.r.a.

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