ML20009H168

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Summary of 810630 Site Visit W/Util in Charlevoix,Mi Re Structural Support Sys (SEP Topic III-6).Attendance List & Viewgraphs Encl
ML20009H168
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 07/31/1981
From: Paulson W
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR LSO5-81-07-100, LSO5-81-7-100, NUDOCS 8108060362
Download: ML20009H168 (18)
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UNITED STATES 8"

NUCLEAR REGULATORY COMMISSION o

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July 31, 1981 Docket No. 50-155 LS05-81-07-100 LICENSEE: Consumers Power Company (CPC)

FACILITY: Big Rock Point Plant

SUBJECT:

SUMMARY

OF SITE VISIT On June 30, 1981, members of the NRC staff and.their consultant visited The purpose of the visit was to view the the Big Rock Point Plant.

structural support of systems important to safety from the standpoint of withstanding a seismic event (SEP Topic III-6). A list of attendees is enclosed (Enclosure 1).

Prior to the plant walk-through, CPC's consultant summarized the seismic risk analysis for the Big Rock Point Plant as used in the Probabilistic Risk Assessment. Copics of the viewgraphs used in this presentation are enclosed (Enclosure 2).

A summary of observations made by the staff is provided below:

1.

Fire Protection System thread connection for elbow, tee, etc a.

b.

no lateral support for long pipe run i

2.

Masonry Wall inside Turbine Building no reinforcement (per site engineer) a.

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electrical equipment room is housed by masonry walls b.

safety related equipment either attached to it or sit next to It c.

3.

Most piping (inside and outside containment) - no lateral support; only vertical hangers were observed 4.

Emergency Condenser Support a.

8 bolts were provided at each saddle support. Analysis is needed to demonstrate its adequacy b.

bolts at slotted hole side of support saddle are not long enough to completely engage all the thread.in the nuts 8108060362 810731 PDR ADOCK 05000155 PDR

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Emergency Condenser Return Line x-a.

apparent excessive displacement was observeo (pushed by hand or j

kicked by foot) b.

Impact between pipe and floor penetration was observed 6.

Electrical panel at end of spent. fuel pool - no positive anchorage or tie down (discussed with P. Yanev, CPC consultant)

~

The above items should be analyzed to determine the safety significance, if any, and modifications made as required, i

The above observations were sumarized by the NRC stdff following the plant tour.

In addition, the NRC staff reiterated its position that the PRA treatment of seismic design adequacy is n7t ecceptable. The staff cited lack of information regardirg design margins of safety related equipment, lack of baseline analysis to extrapolate system capabilities to resist a seismic event, and the fragility data used in the PRA are not applicable to Bi,rtock Point. The NRC staff indicated that simplified analysis methods such as the chart method could be acceptable. Tha staff also stated that the licensee should submit proposed modifications,for our review.

d((i A, b d A-Walter A. Paulson, Pro, ject Manager Operating Reactors Branch #5 Division oflicensing

Enclosures:

1.

Attendance List 2.

Viewgraphs

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OSEE ATTACHED FOR PREVIOUS CONCURRENCE 5

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OFFICIAL RECORD COPY usam mi-m. sea nne ronu a a oo-so) nacu ouo

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Emergency Condenser Return Line a.

apparent excessive displacement was observed (pushed by hand or kicked by foot)

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b.

Impact between pipe and floor penetration was observed 6.

Electrical panel at end of spent. fuel pool - no positiv'e anchorage or tie down (discussed with P. Yanev, CPC consultant)

TheaboveobservationsweresummarizedbytheNRCstafffollowingtheplant tour.. In addition, the NRC staff reiterated its position that the PRA treatment of seismic design adequacy is not acceptable. The staff cited

[

lack of information regarding design margins of safety related equipment, lack of baseline analysis to extrapolate system capabilities to resist a seismic event, and the fragility data used in the PRA are not applicable to Big Rock Poirst. The NRC staff indicated that simplified analysis methods The staff also stated that

% such as the chart method could be acceptable.

3 the licensee should submit proposed modifications for our review.

ff

  • / /// JR_

p Walter A. Paulson, Project Manager Operating Reactors Branch #5 Division of Licensing

Enclosures:

1.

Attendance List 2.

Viewgraphs l

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me ronu ais oomi scu ono OFFICIAL. RECORD COPY usam mi-m.wo

e 5.

Emergency Condenser Return Line apparent excessive displacement was observed (pushed by hand or a.

kie,ked by foot) b.

Impact between pipe and floor penetration was observed 6.

Electrical panel at end of spent. fuel pool - no positive anchorage or tie down (discussed with P. Yanev, CPC consultant)

The above items should be analyzed to determine the safety significance, if any, and modifications made as required.

The 'above observations were sumiirized by ihe NRC staff fe;:owir.;, the plant

~

tour.

In addition, the NRC staff reiterated its position that the PRA treatment of seismic design adequacy is not acceptable. The staff cited lack of information regarding design margins of safety related equipment, lack of baseline analysis to extrapolate system capabilities to resist a seismic event, and the fragility data used in the PRA are not applicable to Big Rock Point. The NRC staff indicated that simplified analysis methods such as the chart method could be acceptable. The staff also stated that the licensee should submit proposed modifications for our review.

hahL A.$d~

Walter A. Paulson, Project Manager Operating Reactors Branch #5 Division of Licensing

Enclosures:

1.

Attendance List 2.

Viewgraphs

l.

g ly U. S. Environmental Protection '

Mr. Paul A. Perry, Secretary Consumers Power Cogany Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Cogany Chicago, Illinois 60604 212 West Michigan Alenue Jackson, Michigan 49201 Herbert Grossman Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatcry Comission Joseph Gallo, Esquire Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Dr. Oscar H. Paris Room 325 Washington, D. C.

20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Peter W. Steketee, Esquire Washington, D. C.

40555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Comission Atomic Safety & Licensing Appeal Board Washington, D. C.

20555 U. S. Nuclear Regulatory Comission Washington,*0. C.

20555 Big Rock Point Nuc, lear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Bcx 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Charlevoix Public Library Route 2, Box 108C Charlevoix, Michigan 49720 107 Clinton Street Charlevoix, Michigan William J. Scanlon, Esquire 2034 Pauline Boulevard Chairman County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Roca 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Mr. Jim E. Mills Council for Christa Maria, et al.

Route 2 Bu 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law 263316th Street, NW Thomas S. Moore Washington, D. C.

20460 Atomic Safety & Licensing Appeal Board U. S. Nuclear Regulatory Comission Washington, D. C.

205

-.4-Dr. John H. Buck Atomic Safety and Ltcensing Appeal Board U. S. Nuclear Regulatory Connission Washington, D. C.

20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers. Power Company 1945 W. Parnall. Road l

Jackson, Michigan 49201 O

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. - ~ - -. _

ENCLOSURE 1 ATTENDANCE LIST BIG ROCK POINT SITE VISIT JUNE 30, 1981 W. A. Paulson, NRC T. M. Cheiig NRC W. J. Hall NRC Consultant W. T. Russell, NRC P. I. Yaney, EQE, Inc.

W. Brinsfield, Wood /Laaner Assoc.

D. VandeWalle, CPC Nuclear Activities Dept.

R. B. Jenkins, CPC D. P. Blanchard, CPC R. Huston, CPC Bethesda Licensing Rep.

P. Donnelly, CPC R. A. Vincent, CPC G. C. Wright, SRI NRC

ENCLOSURE 2 SEISMIC RISK ANALYSIS FOR THE BIG ROCK POINT NUCLEAR PLANT PURPOSE:

- DETERMINE -CONTRIBUTION _TO RISK FROM SEISMIC EVENTS AT BIG ROCK POINT

- COMPARE COST / BENEFIT RATIO FOR SEISMIC AND I!ON-SEISMIC EVENTS

- DETERMINE WHETHER SEISMIC EVALUATIONS SHOULD BE A TOPlc 0F SIGNIFICANT ADDITIONAL EXPENDITURE METHODOLOGY:

- OBTAIN SEISMIC RECURRENCE INTERVAL CURVES

- OBTAIN FRAGILITY CURVES FOR COMPONENTS AND STRUCTURES

- SYSTEMATICALLY DETERMINE SEISMICALLY INDUCED i

COMMON-CAUSE FAILURE SEQUENCES 6

USE NON-SEISMIC COMMON CAUSE EVENTS AS A BUILDING BLOCK TO LOCATE POTENTI AL PROBLEM

AREAS, E.G.,

FIRES, HIGH ENERGY LINE BREAKS INCLUDE COMMON-CAUSE EFFECTS DUE TO LOSP I

e f

AND GROSS STRUCTURAL FAILURES (AS INDICATED BY FRAGILITY DATA)

ROBABILITIES USING BEST-D

- ESTIMATE SEQUENCE ESTIMATE ANALYSES

- DETERMINE CONTRIBUTIONS TO IOTAL CORE DAMAGE PROEABILITY 0

IF NO SEISMIC CORE DAMAGE SE90ENCES EXIST WITH PR03 ABILITIES 1 10~ / YEAR (THE ESTIMATED FREQUENCY OF A "LARGE" EARTHQUAKE) THEN j

~

CONTRIBUTION OF SEISMIC EVENTS IS

  • 1% OF NON-SE!SMIC CORE DAMAGE PROBABILITY (AS IDENTIFIED'IN PRA) e IF ABOVE STATEMENT CAN BE MADE, FURTHER LARGE-SCALE EXPENDITURE ON SEISMIC ISSUES l

APPEARS TO BE UNJUSTIF1ED l ---- - - -- - - - -

CRITICAL SYSTEMS AT BIG ROCK POINT

- CRD

- EMERGENCY CONDENSER:

INCLUDING DEMINERALIZED WATER MAKEUP LINE AND PUMP

- FIRE PROTECTION SYSTEM:

ESPECIALLY FIRE PUMPS CORE SPRAY PUMPS CORE SPRAY LINES ENCLOSURE SPRAY

- RDS

- POST-INCIDENT SYSTEM

- CONTAINMENT ISOLATION:

MSIV VENT VALVES

- EMERGENCY POWER SUPPLY

- DC POWER SYSTEM

- RCS

- INSTRUMENT AIR

SEISMIC RECURRENCE INTERVAL CURVES e

RECURRENCE INTERVAL CURVE AS USED IN PRA IS NOT SIGNIFICANTLY DIFFERENT THAN OTHERS CURRENTLY AVAILABLE, E.G.,

DRESDEN SITE (TERA /LLL ' ANALYSIS)

)

ZION SITE (SSKRP/LLL AMALYSIS)

BIG ROCK POINT SITE (TERA /LLL AM LYSIS)

(NOTE: SSE PEAK GROUND ACCELERATION FOR BRP = 0.12 G) i I

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+

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.. =.

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9

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p.

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s,.y. y..,ih3, g (c)

,c

1 FRAGILITY DATA SOURCE:

SSMRP APPLICATION:

- USED TO DETEMINE UNAVAILABILITIES OF COMPONEt!TS AS A CUNCTION OF EARTHOUAKE INTEt!SITY

- U!'!AVAlllBILITIES USED AS INPUT FOR SEQUENCE PROBABILITY DETER!'INATION

falets VI.F3 f, ras.it 11Y _ot 5tallPIIni45 atIihtw't 0,10 It trait stin ty itner4 u#tiew.trilu, iLtK4 Settseg

~

l its(g gggjiggg UII[

'803AN Mf DI Aie p

Irt 5 torr',[

s a

8' FAltuRC IRAGillif pp[gututi f*8*IFC CAPAcj)f LAPA(llf l ACluft St ) Mar'4 (tsg*gg i t(

RAhutet LintRIC CAllG0ef Ismg[$)

ripantita 5.all-redtu leerimental and Structural Supports. Zero Period RI 14

'W4 26g 0.21 1.25 c.31 32.51 0.31 0.76 c.rf g

S tvra stal mter Drives Pumps Seals. Bearings.

Acceleration Coup)ings

'snJ Co pressors

~.. -

g 63, o.g3 o,33 o,q3

_'7 35g 0.31 1.01 c.43 i

Defosmaation impairs Peak Spectral cre<tuency at t

Hydreastic and Air Operated Au eler a t t un Peat 5a fuction Vaters38*

Deformatibn impairs Peak %pectral f reque sny at 51 Jag 0.32 1.81 p.9) 199 0.54 0.31 a.44 g,y thett, Speing Relief anu Acceleestlun f*eak Sa g

Man 6al Valves v5*

Tunctiun

~ _. _

5e ll Mistellaneous Valees Defcasation impairs Feak Spect:41 Irequeeny at 51 33g 0.31

.l.d1 n.41 e,vg 0.53 0.31 i

o,43 y*y' i

i f*cak Se

<n* (tstept Putor Ot. crated) function Accelerettun.

Case Cracking.

Spectral 5 10 8f t 53 4.79 0.16 1.75 o 34 5.?$9 0.37 0.26 0.21 3

Plate tallure Acceleration

.(

ettterles Structural Spectral S "I t's

'>t 10.19 0.21 1.25 0.34 43.49 0.40 0.76 0.30 g,5 Isensfu ners l

-.f..i failure Ascelev a tion Air (undit tentw; and Air Misc. funstfunal Spectral 10 30 l's 41 9.59 0.24 1.75 u.33 I s. g.s 0.41 f

0.71 n.3I failuees Acceleration lundling Pc,wer lini?

tusal Instruments and Electrical Jero Period Rigid I HA 3/.ng U.3?

1.25

p..s1 l a ),

0.45 0.7s o,3q Halfusution Ac t elera t ion f

j transmitters y -. -

.g......

e 3 ?%f

1. org a% I l.s3 4

g

{

le en,' (o ts ol telulpsent Relay C1.atter Spetteal 510 Pt 51 7.t e

!.59 1.?S es y, ba (lestrecal lustrtamenitation e

I At t elerat lust 0*

Instuding:

__ q itelay or Dreater Spectral 5-10 t's 51 1.19 0.73 1.75 0.1%

v. s,.;

o at I p.41 c.e.6 4<

j

^

.t Parmt & tech Act & iat kn

14. fig 0.8 1.75 G.35 In.7y 0.e7 c.47 c.13 4

Lontial Pos.els & Rocks l

51suctural Spec tral 5 10 fli SI j

(

treaner Panels

{

t l

.. g t

r trol Centers faHure Accelera W e a

r t

.3.

.....{.

~

Dlisite Power fa'lus e of Ceramic Peak Cround ta g hA l

0.79 0.32 flA td.

u 2y 0.J2 O.73 0.75 E.

Ir.verters

.._.g I

'!.... 'I e

.l._.

t In.ufaturs Acceleratist l_

k......_ I -

(J) t e cquency cited teflects it.e f a r.p.e sy e. se of ts.e s.at te,y e at; systr,

Notes: (1) Acceleratio. capacities cited may lie lower for seismic induced time leistory saputs. Capacities are derived f eted synthesised sis e f eet In;.uts of Matteries are cons blered revi.f.

2 5 seconds ifunation ubich may have less energy tuntent thah an vartIpeuale (4l f l agIll(y pat ashqrter lh tjeI tt+.! a t L a t i.ag t / s t e ten f us e ints0 fate.

If age'. ej ss tjalli t y I e..%es -

f et = cabinet t>ase ta critical. i.uw ? rs salu.icJ in Jerleattues ut f s ags tity live feistcry legt that oislJ result in the same re" cense spettri.e.

tr ial raperten e st.aus. he..cr that this category of etsi *eht 1.45 s.tt p28ameter.

t heen severeIf d.ed.lged in bajUr seIsic events.

(5) %Idrs up to 1000 nA,13,ttu0 4bu v.

s (6) fsiwaliihturtaal Data. f ute.fsat 'rayelity s as amuter is peak giound attelee stlun,

~

(;) Valves are assword to t,e line mountei.t and the Is agility parameter c,f ten.seen is peak atteles at tun of the piptsig systes at it e valve lutation. Capacity is t,ase.J ups.n peak spests al Mcelte at suh uf it.e test trecte a.

Desponse f a'.tues th late'e 2 re f les t the probabili t y that line mauntrJ walves will actually esper ience the peak spesteal att eles atit,* uf (f.e J!*; ills ahf r f esaur s;eests a.

e a

e e

e m.

. ~ - - -

.JT' l,

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4

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6 O

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e

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. -..e.

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.=

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. ~...

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..... _ ~...

y

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....... -.... -... +..

. -. +........

m m

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l A

l M

s.

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.A C

g I

m g

h

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,,.T i-e

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t

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=.

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a t.

-. 1 u- :.-

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.L..'. :.. ' '..

2...

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i

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a I

e I

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s.._s._-

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  • -i

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..t..

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t f

C

'O O

C

.A: u..tqetteneun VI-146

SEQUENCES 4

CONSIDERED IN PRA:

LOSS OF FEEDWATER LOSS OF 0FFSITE POWER COLLAPSE OF EMERGENCY CONDENSER i

COLLAPSE OF TURBINE BUILDING ROOF i

MAJOR COMPONENT FAILURES:

ELECTRICAL - RELAY CHATTER CIRCulT BREAKER TRIP MECHANICAL - EMERGENCY CONDENSER SUPPORT PEDESTAL TURBINE BUILDING ROOF BRACE 9

I i

l l

I l

l -.

SUMMARY

OF 00MINANT SEQUENCES (BIG ROCK POINT PRA)

Secuence Class (ho. of Secue.:es)

Frecuency (yr'I)

Turbine Trip (3) 9.0 x 10'7

-7 Loss of Feedwt*?r (1) 4.3 x 10

-6 Lt,ss of Main Condenser (6) 4.0 x 10

-6 Loss of Offsite Power (15) 4.7 x 10

-5 LOCA (5) 4.5 x 10 Steam Line Break Inside 1.1 x 10'#

Containmen (3)

-5 Loss of Instrument Air (6) 3.5 x 10 Spurious Closure of MSIV (4) 3.2 x 10-6 Spurious Opening of Turbine 7.1 x 10-0 Bypass Vaive (5)

-5 ATWS (D) 2.7,x 10 Spurious Opening of RDS 1.7 x 10~0 Isolation Valve (2)

-6 High Energy Line Breat (2) 1.5 x 10 f

Interfacing LOCA (2) 9.1 x 10 "

~

-4 Fire (5) 2.3 x 10 1

Stuck Open Safety Valve (8)-

2. 9 x 10-'

TOTAL (Si secuences) 9.75' x 10 i

o i

i e

l t

CONCLUSIONS

\\

i o

SElSMIC SEQUENCE PPOBABILITIES ARE LESS THAN CP EQUAL TO 10-5fygg; o

SEISMIC SEQUENCES CONTRIBUTE VERY LITTLE

(~ 1%) TO TOTAL RISK OF CORE DAMAGE AT BRP o

COMPARISOPS WITH OTHEP PLANT S'TES (E.G.,

ZION, DRESDEN) INDICATE SE15'.lC '.!SK AT BRP IS CONSIDERABLY LOWER THAN OTHER SCT,FOR ZION)

PLANTS (1% VS.

N i

i I

o SIGNIFICANT EXPENDITURES ON SE!SMIC ISSUES ARE NOT WARRAFTED WHEb' COMPARED TO EXPECTED BENEFIT FROP MODIFICATIONS IF OTHER AREAS (E.G., FIRE SUPPRESSION, Et'ERGENCY CONDENSER MAKE-UP, ETC.)

DISTRIBUTION FOR MEETING StJI9tARY LPDR TERA NSIC ORB #5 RF.

D. Eisenhut g,

G. Lainas g

D. Crutchfield

'V)\\

H. Smith ORB #5 PM - W. Paulson J. Olshinski e, g7 %

ACRS 10)

/

pff T. M. Cheng 4

W. J. Hall, Consultant W. Russell.

P. I. Yanev, EQE, Inc.

W. Brinsfield, Wood /Lecner Assoc.

D. VandeWalle, CPC R. B. Jenkins, CPC D. P. Blanchard, CPC R. Huston, CPC, Bethesda Licensing Rep.

P. Donnelly, CPC, R. A. Vincent, CPC G. C. Wroght, SRI, NRC e

_. _

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