ML20210U101
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| ML20210U101 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/29/1984 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20210T938 | List: |
| References | |
| FOIA-86-266 NUDOCS 8606020172 | |
| Download: ML20210U101 (11) | |
See also: IR 05000255/1983074
Text
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- ATTACHMENT 2
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August 29, 1984
MEMORANDUM FOR: R. L. Spessard, Director, Division of Reactor Safety ,
FROM: C. E. Norelius, Director, Division of Reactor Projects
SUBJECT: REQUEST FOR ASSISTANCE
(Evaluation of LER 50-255/83-74 for Palisades)
,
Attached is a copy of a written report of an event at the Palisades
unit dated November 9, 1983. As discussed between W. G. Guldemond and
G. C. Wright of our respective staffs, we understand that you plan to
review the attached LER (50-255/83-74), EventReport(E-PAL-83-204),
and internal CPC0 memo and to provide your position as to the safety
significance of the event,
d
"Griginal signed by .R. F. Warnick
C. E. Norelius, Director
Division of Reactor Projects
Attachment: As Stated
cc w/o attachment:
G. C. Wright, DRP
W. D. Shafer, DRP
B. L. Jorgensen, SRI
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8606020172 860516 .
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PDR FOIA ,
MURPHY 86-266 PDR l
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y Iata: _Valies_fgile_d_to_ Meet the ' A_slp_und ' Actepiante_fr_ileria FouncLin Tecanica1
Pnecirlcatinnn Test _RW P9
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04110 levie.c.: . (tassnni
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13107 rw or neRV-0701 - -072L_
d usce er.0 0, uc.en.ct ce c>ea.0 -
valres_at__the_BC_Cobb_. Plant .
On 10-3-83. SE&Ls_ began testina Palisades r.ain steam relief
en pl eted_ on_RLD701_thronch RV-D721. Iterveen_ott . L anroet. IT. the 'as f_o3uld test _n vere
RV-0715..vas_found_vithin the +nct
remn i ni n e, 23_rel i a f valve n vercJnnna vith l i f t pn i nt e that e;enaded criterjn-
4
The
critarin. the tb
_In n11 enene the,lV l i fted in_evenec nf the +15 evitorise. Th o ' p *ift
pointn vere aveceded from n lnu nf 1_35 tn n mirm nf 11g_9 0 Theep vniven ve"a
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re-a g21 anri g tha 1==t va rn al i n g nut:y n and
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Tn all races, t M y *a
Osan acrac.: _
\M WN W *2U "
Each vn1va hae.heen Mi nn ena-bled and rebuilt by the crashy__ Valve Cn-
New internni pnrts_bava_baan reninead where naadad- All r*liaf valvenservice hava haa"
rep-
ratested nna maet the_acceptnnch eviteria._enll ed fnr in R"-29
1.1 strut.us: Tg Tent p wpg. nort.g Tent p-nc _ F,) "t"n0 s' EEr_i_qhfg
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! PEVIEV A';D NOTIFICATIG's =
A_) att0stant r0 .ec; ; PART 2
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RVs in 4vu.-l)-Elea2e_ cansuit*-ydtMSU9 rf%h wra N Y Md'%
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1981 (when ,
r,,y3etpoints were_rnund lov) nna in- thin inntance 1084
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7"AnV_ yere found hir bl_.tD__ dater,-ine A M M M'(when en
.sySte _itic_causes_Eay have eYisted_to__cause_then_n11(nna report __to_ A CARB nn n
Refont '81_ 9) % 3.-1g7atg_ng -
notential
to be_. Set high._at_the__end_of
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Uhen_these valves _v.e _.
As_a_ renult._the_aten
dineharga rn+a- Thie une anna lift _ height (ie_discharze_ tapacity) was adtusted .
to li
tatiya_v.ho_assurad tha a ftar__cnnsulting_vith_the Crosby Valyc_ Co. represen-
1ilt_nressure- test engineer tha_t this adjustment vould not effect the valve
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* (N a4 I * COPF $ = FCesset to 44 WPoe (Caettt#0. OF Paar 3.
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I"* 8 I * f0 esse 0 TO Ga weeg (Oaattisce os paar 3.
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FORWARD ALL CORRECTIVE ACTION 00CL*ENTS THR0tKN YOUR CORPICilVE ACTION ,
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GONTINUdTION SHEET
rcea ca-20 (moit SECT 80m 10 WalCII &Dcefl04tL teFoestattosi APPL egs) PaCf ~ CF ~
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Part_._1C,_Descr_intjon .o_f_ Occurrence or Condi_ tion:
2
(cont.)
__
fnund tn be leakine,_ bad.ly_ani_re. quired reset 11 NIL.to__rael_the_Aec2Rtance
criteria. That_adlustr.ent_r.av be_ the reason for the high lift coints
en,ma auring tha lor 3 ta=te.
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Par _t_3B_IVALUAT10N__AND_ DISP.0SLTION__ ROOT CAUSE fennt.)
__
After reviewing the test data. I disagree with the Crosby representative. The. valve
dischnvra majnetrant di d affect. li ft preennren. T believe that the fnlln'Iirgq_.s e e" 4 * i n _ __
took pince- -
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l. The valve discharge heights were adjusted in 1961.
2. "The valves vere then tested'and consistently found to lir_t_at_a3ver *
3. The rressure_than reiuired.
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h. valyes were then read.1usted to a higher lift pressure. .
9. They were ratested_vith the ad iiie,t.{di sc h n rge ' heights and tested Rood.
The vni va aiceherra haichte vere renainnrea tn nricinnl
reinslalled.
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* d e m i en and the vn1 van
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In 1983 the valves were retested without adjustment using a test rig with -
a large accumulator.
-
reenived.
The valves consistently lifted at a Ic m pressure than
Fff ;;-
Cs. m.
Wdd
Theg
I nva.- ad N:.--.en t to the valve dis _ char e_.heichti ciu~sedEl the' valves to Iift at s-
* ~aecura ukan +actea Tha vn i va lift nainet ante en a a' lor 1 nn1v en-ma-e=taa
for__the dischar.ge height._adlysfr.ents . When tested in 1983 theinvalves
g3 thay vould in s ervi c e .
Dai-form' d e
A1.l~the Main Steam RV's have been rebuilt and tested, without discharge height
_
adjustment, using a test rig that simulates actual plant conditions. , f-
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'pza',. CORRECTIVE ACTION SHEET E
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D'ALCATION , T
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coe, n . gree te.) reewaes to =u
I'3a&I * .t0ef 3. pop.ae8 70 ga eron to ntae tettesses acanesstaates e*os conettfece er raat 3; (rce es e ano mes . esscans).
(C.aae,). w
t(730s Of Pael 1.
Mitel * t0Pr 3. fge aat 70 ones,naf set steseteget D70s (Caettif Cg er past g.
(CFT t . rette In 90ftatef (24180t tim 1te W'Je to.*ttfles Of raaf 3. l
FDPEG ALL CORRECTIVE ACTIO!! DOCC*ENIS THCCGI YOUR CORRICilVE ACTIO:t C00Eli;ATOR! -
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CONTINUhllou SHEET
;3 (aroff SfCleces 70 teset(# A03Elecsat e st 0A*iA T I Oes APPL e t t ) -
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De_qs_ign_f_unct main steam ion . relief valves (RV-0701 thru RV-072h) are canable of cerforming their
found' set ooints.The results from 1981 R%_2_9_t_esting indicated extremely _lov 'as
from predescribed factory setti_ngs.These values were obtained after the nozzle ring was_ajilu
_.
The nozzle ring _a_djustment was necessary_t_o_de-
_cdesired
te a ss_ blowdown d
steam generation capacity. u e_t o_ tnt __.syS_t t
e_ q_l imit at i ons ,_i_e, _t.ht_tts1_sy_sita.f iLD o
_ inspected,
cated that cleaned set oointand was not affe'eted by nozzlT ilng_adj~ustment.The
retested. -
valve manufactur
-~The valves were
The
achieve or_ooer lift. Reps 1Jtly.e__1.ifts were cerformed to demonstrate rel.iability. spring tension was adjusted { increased) to_ ,
. Upon cocoletion the nozzle ring was returned to the factory setting and lock vired. --
_Ibe 1083JX-29 tentlnc indicateLextre:aly_bigh 'as found' set coints. Th ese_._y_a_l_uts '
_Sete_imprnY.eChetween_1981o_b_tain e.d_.xit baut_prio and_19&.'i. r_ adiu st r.ent s . The_1981 te.st system steaq_cepacity was -
_ _gs sary. Therefore. the_ nozzle _rjnr adlustment was __p_t_nec- n --
The -valves vere insoected. cleaned. repaired and/or relanped under the direct
supervision of the manufacturer's field service representative.
tested with the spring tension adjustid l ecrease~d) to achieve procer lift.The valves were re--
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Repetitive
pipe
for Isak_tJghtness. _.yas_ removed - _and at 40jlof_ set _. point. prissure the_.ya
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In_recent_ telephone cony _ersations vith D. A. Desnover (CPCo - TraH '
__Tuttle (Crosby _ Company Stre_cil_and_D.. --
_ _. set point relationshio was clarified.- engineerind the_Cr_qsby_ position on the _nnule ring and _ . _
the-- nozzle rinc is adjusted it is usually No_xg_al_ly only . the nozz_le ring is not adlusted. . I f__ ;
f a
f .1_a_ ins _that nqr_nal, minor __ adjustments vill not affect set point _.one They to added three-that . notches..'!_.
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192erincl.he_ngizle_
cause a sli ring .of s.safetv =alve c ?,ld i ureta ver. TTeh el.an i e wld
was in 1M1[cht__incre m ir. ct.r i ..: :.rw.aute . -Cpr_.v.;r+1 2 ;.,_iW_r.j_s-iire -er.:
_bs it
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sure. raising the nozzle ring could cause a slight decrease in ooppine pres-
During the 1981 testing the nozzle rings were adjusted as mucE Ils 12 "dotches. -
, -
In addition,
valve . _ Vendorthe instructions
. File.EI.-F-.D bulletin
, _ state s_: for operation and maintenance of Crosby safkly
. . _
._
"If the valve pop _s too lov. the seats may have becgme damaced. _ Low popping
pr.
cog:pon essure cause._._is_ " seldom caDERd_by_ Spring _ set.. althouzh this is considered a
_.The_above information ind_icates_that set points can be influenced by seat condition ~
__and_no J_le_f_ing Ad,1ustments,although_the exact relationship can not be determined.
_ enced
Sufficebytoleaking state that valves theand 1981 R'4-29
nozzle ring'as found' test results were in error, infl'u~-
adjustments.
The corrective action (soring
tensioning)_taken
_during the 1983 testing. durin5 the 1981 R:1-29 test caused the deviations observed / recorded ~
As stated above. the main steam relier valves (RV-0701 thru ltV 072h) are capable of
.
.. of_the ;1903
__ performing _JE-29_ test _._has_the_. adjustment _bplt _
_.
_Q1;;ple_ltontrg1S
retur_ned
tion -
_.in_v_ithin._.l 25_ flat.s_at_the_'as_found '._positipa_qr._the._19&LBM-29..t.es_t_.__ ln additio
_they__hayt_ individually _bten_. inspected < for_ lea}s__tigh
._g_uppott.ive evidence can be shown (see _ Attachment 1)tniss.. Non-conglysjve but .
__numetical
_
__19633M-29_average tnt.s. of the observed 'as found' lift _ point during both the 1901 an_dThe bo
hand _ AllbDt_pne_YA.lve_.f_ alls _yithin_th_e recommeAd_ed set eqint__t_ ole _taDee -
_
%e aggreEate of the above
_ - informafi_on is the basis for the concluYionT'sef,~for'th.
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Nuclear Plant
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ENGINEERING ANALYSIS WORKSHEET
Title: ;5L ef- i .j s t. J G .- (?J - o 7e s - GV- o 17 4_ 5 ET!>: 37 Dee r7 bks
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From MJBaker,P24-404f*(J]33 -
CONSUMERS
Date POWER
June 8, 1984
QOMPANY
Subject REACTOR ENGINEERING RESPONSE TO E-PAL-83-204C, Internal
STEAM GENERATOR SAFETY VALVES FAIL TO MEET Correspondence
ACCEPTANCE CRITERIA
MJB 84-001
Ref
1) XN-NT-77-18, Plant Transient Analysis of the Palisades Reactor
,
for Operation at 2530 Mwt, July 1977, and
-
2) Phone conversation, Mel Woolpert, Combustion Engineering,
5/31/84.
Between October 4 and 14 of 1983,' steam generator safety relief valves RV-0701
through RV-0724 were tested for proper lif t pressures. Only 1 of the 24
valves was found to lift with~in the ASME code acceptance band of 11%. Event
Report E-PAL-83-204, part c raises the question of the impact of the
"as found" settings on the existing Palisades safety analysis. The purpose of
this analysis
pancy. is to determine what effect, if any, is created by this discre-
It is the opinion of RED that the Palisades plant was not in an unsafe
condition as a result of the a's found" safety valve settings. However, the
~ plant was in an unanalyzed and potentially unsafe conditior..
basis transients (Ref 1) . challenge the secondary side safety relief valves.Four licensing
E' The
analysis.increased lift pressure would alter the results of the above mentioned
valve setpoints However,
wouldfor
stillthis case,
yield it is our belief that the "as found" sa fety
acceptable results for the transients in
question. Regardless, it should be stressed that:.1) our findings are based
on engineerings approximations, and 2) increased drift in these setpoints
could create an unsafe condition.
to insure safe operation of the plant.We recommend that this problem be corrected
If it remains difficult to hold these
values
(Ref 2) within the 11% acceptance band, a widening of the band is possible.
The
follows:four transients which challenge the secondary safety valves are as
.
A. Rod Withdrawal from 102% Power,
B. Rod Withdrawal from 52% Power,
C. Single Control Rod Withdrawal, and
D. Loss of Load.
Transients A, B and C reach minimum departure from nucleate * boiling ratio
(MDNBR) at the time of reactor trip. The secondary safety's don't open until
a considerable time af ter trip. At that time, DNBR has increased and is no
longer an important factor. Primary system pressure remains low during these
transients, never being greater than 2210 psia. Therefore, the safety valves
have little or no affect on safe operation in these transients. However,-the
loss of load transient' challenges peak primary system pressure (52750 psia)
primary ,
seconda ry AP (51530 psid), and MDNBR (21.30). In this transient,
the secondary safetys are need to relieve pressure in the carly stages ,and .
.
_
--....
, _ _ . _ . _ , ,- -
*
. .
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.
a
2
.- ,
.
therefore are an important element
event. in mitigating the consequences of this
. .
Three loss of load cases were analyzed in Ref 1.
is the worst
with respect to peak primary pressure.(See attachment 1) Case 1 *
effectvalves
safety of delay
weresafety valve
assumed not opening on peak primary pressureAttachment
,
2 sho
to open until the highest
.
The secondary
for group I was reached, clearly a conservative assumption"as found" setting
.
pressure
tion limit., reached 2450 psia, much less than the 2750 psia technicalPeak specifica-
primary
Attachment 3 shows the estimated AP secondary
setpoint as a result AP . of a secCas
for group 1 of 1037 psia, as in Case 1.
. ondary safety valve
' psid, well below the limit of 1530 psid. The approximated AP = 1424
technical speci_fication. Limit on DNBR of 1 3 .Case .
3 challenges the Palisades , _ ,,
Reactor Engineering feels that delayed safety valve opIn this case l^DNBR'= 17
effect on actual fuel performance. Other Torms 'of see'o denin,g wo_uld.have little..
are. conservatively ' ass'uded inop"er%fE 'fo'r' 'thiscas e.
-
n ary pressure . relief
atmospheric dump valvesand' 'c'onde'n's'er' bypass would be' a.In reality, -the
pressure. .
r-
of the W-3 DNB correlation which hasm aoflicense ,- , is DNBR
1.3. The more
the use li itAn
provides additional operational margins. oaccurate 1.17 whichXNB DNBR c
sufficient margin of safety, to offset the change inWe feel these conserva,tisms yiel
. .
safety valve setpoints.
Therefore, Reactor engineering concludes thata the ...P li
an unsafe condition due to the improperly set valves. sades Plant was not in
-
However, the valves
the existing safety analysis.should be maintained
~
at their required s
within the bounds of
<
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IC0684-0003A-RE03 _
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LOSS OF LOAD TRANSIENT RESULTS: ; i. ': '
. - < ,,.
Initial ~
. 1. .- ..
Initial
,
.
' , , i> t-
:: tmary Secondary Allow Pressurizer Allow Atmospheric' */
,
Max. aP**
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-Case _ Pre'sure
s
Pressure Relief Valve Steam Pump and'j
Peak * During '
'
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Opening and Spnay, Condenser Bypass,j [ Pressure Trans ient
,j , , ' ,, ..psia
-
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....-,
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MDNBR
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1 23'94 ~ 1371 1.55-
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2 2110
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Technical specification limit on primary pressure is 2750 psia :
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Technical specification limit on primary-secondary uring AP istransients. 1530 psid d
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3-fi company
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Geaeres omces: 212 west uscassen Avenue. Jochton. Mech gen 49201 * Aves Coce 017788 0330
'
December 9, 1983
,
James G Kepplet, Administrator
Region III
-
US Nuclear . Regulatory Coc=ission
799 Roosevelt Road
Glen Ellyn IL 60137 .
DOCKET 50-255 - LICENSE DPR-20 -
PALISADES PLANT - LICENSEE EVENT REPORT 83-74 (VALVES FAILED TO MEET "AS
FOUND" ACCEPTANCE CRITERIA) , ,.
.
Attached please find Licensee Event Report 83-74 (Valves Failed To Meet "As
Found!' Acceptance Criteria) which is reportable to the NRC per Technical -
Specification 6.9.2.b(1).
Brian D Johnson (Signed)
, .
Brian D Johnson
Staff Licensing Engineer
CC Director, Office of Nuclear Reactor Regulation
Director, Office of Inspection and Enforcement
NRC Resident Inspector - Palisades ]
j
Attachments !
.'
,
evwr
I
, OCl283-0004A-NLO2
< _
f
. M
~., . PALISADES PLANT - DOCKET 50-255
-
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, u.s. Nuctas.= ntoutATony couuiss oN
LICENSEE EVENT REPORT
CONTROL SLocat: l
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3. 91813 .n J.@
..
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EVENT DESCRIPT80N AND PRO.a.LE CONSEQUENCES h
;o ! 21 I While shutdown for refueling, e routine refuq1inc duration surveillance tesy
[o [3 y I revealed that fourteen of twenty-four cain stee.= relief valves lifted at
lo la j Ipressures in excess of the urner lirit sreci fied in TS ~4
1.7. '
. , "w . v n '1 9.- ! c.3
Io i s i I are believed to have been able to provide their intended safety functione I[
o s 152cvever. evaluation is incorplete at this tire.
Notification vill be r o- I
;o g ,4 j vided if final analysis is to the contrary. Reportable per TS 6.9.2.b(1). '"
; w at
o . l (The valves have been disasse= bled , rebuilt end successfully re-tested.) !
... *c'l'o's" 'c^o$ s$$s eop.o= =Tcoor
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L.IJO 'v' o f o! o I o.o f LIJ@ 1xJO. LA@ . .f c 17 11 IOI@
22 sa 2s 2 ai
u .,
, CAUSE C($0RIPTION AND CORRECrivE ACTIONS h .
,
i o ICeuse is believed to have resulted frc ad_iustrents rede to each valve's I
m i bl evdown ring which affected the lift setting. These adjusteents were cade
, g subsequent to the final lift setting adjusteents cade during the 1981
i 2 l Refueline Outere. The test rrocedure vill be reviaad to rrevent bl evdevn I
,
,
i adjustments prior to "as found" testing, and subsequent to "as left" testing 4
. .
AN s rouwt m oT=gn gTatus D o a oescovtav otScaerTeoas
> $
La)@ In i n I nI@l13 un e., e m ~. s. ,,mt i
7 . 12 asi L.P.J@l
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afLEa3fD o#mgLlast AucvwT of ACT1vtTY LOCatso4 0s agtgast
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JGKepple r. Administrator p '
Pelisades I'lant. I
< -
LEP. 83-74 -
l
, December 9, 1983
l l
.
During the current refueling outage, all twenty-feur (24) main steam relief
r
velves were remoyed and cent off-site for surveillance testing par
Surveillance Pf6cedure R!!-29. The results of the."as found" testing indicata ,
that fourteen (14) valves lif ted af. test pressures in excess of ths upper ,
li:iit specified in TS .3.1.7.c. The maximum pressure at which a valve lifted ;
was 1147 psig and the minteum pressure in excess of the TS limit was 1G40 psig. '
a
As described ih F5/S Chapter 4 3.4, the design at Palisades is such that the
hain steam relief valves are divided into three groups, each group having a
l differe,.nt lif t setting. The perfomance of the surveillance test resulted in ,
a total of twenty-three (23) relJef valves lif ting at pressures in ciccess
of the upper limits of the FSAR and surveillance test acceptance criteria for
eveh group; Fourteen (14) of thei;e valves were also in excess of the upper
lie,it impose'd by TS 3,1.7.c as described above.
The cause is believed to have resulted from adjustments made during the :
previous refueling cutage to the valve's blevdown ripg and subsequent to the
final lif t setting adjuste:ent which was made at that time. Adjustments to
_
j
'
the valve's blesado.en. ting uere pernitted by pror.edure. Adjustments to the
blevdown ring were not anticipated to have an effect on the lif t pressure
; value. '
.
The test proceidrs will he re;riecd to probibit any adjustments to the relief
valve blowdown ring prior to "as found" testing or subsequent to "as left"
-
'
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testing. .
'
.
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e
40
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OC1283-00048-NLO2 -
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