ML17054D136
| ML17054D136 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/26/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| References | |
| IEB-73-06, IEB-73-6, NUDOCS 7911130550 | |
| Download: ML17054D136 (48) | |
Text
RO Bulletin No. 73-6 November 26, 1973 INADVERTENT CRITICALITY IN A BOILING WATER REACTOR We recently received an abnormal occurrence report from the Vermont Yankee Nuclear Power Corporation relating to an inadvertent criticality incident that was experienced at their Vermont Yankee facility.
A copy of the abnormal occurrence report is attached to this Bulletin to provide you with pertinent details of this event.
At the time of the inadvertent criticality incident, the reactor vessel and primary containment heads were removed, the refueling cavity above the reactor vessel was flooded, control rod friction tests were in
- progress, the rod worth minimizer was bypassed, and core verification had been in progress.
As a result of the incident, no measurable radioactivity was released, no fuel damage resulted and no personnel exposures were experienced.
The incident is currently under review and evaluation by the Regulatory Staff.
Action requested by this bulletin is contained in Section A.
A.
Action Re uested b
Licensees In,light of this occurrence you are requested to take the following actions.
Upon completion of these actions you are requested to inform this office in writing, within 45.day's of the date of this letter, of the status of each item identified in each paragraph and subparagraph listed below:
1.
Procedural Review a.
Control Rod Drive 0 eratin and Testin Procedures (1) Conduct a review of your control rod drive operating and testing procedures to determine that approved procedures exist for all operations and tests.
(2) Verify that appropriate prerequisites are included in the procedures to require testing of associated interlock and protective features before control rod testing is permitted.
(3) Assure that prerequisites and detailed instructions are provided that demonstrate compliance with technical spe-cification requirements and design bases.
i
b.
B ass Installation Procedures Jum ers or Liftin of Leads Assure that existing bypass installation procedures have been conservatively reviewed for technical adequacy and for adminis-strative controls.
c.
Radiation Protection Procedures Assure that procedures for access control and personnel accountability in areas subject to accidents are current.
d.
Shift Transition Procedure Turnover Assure that complete and detailed procedures are in effect that provide instructions for a proper and conservative turnover of shift responsibilities.
Such procedures must include requirements for communicating the status of all safety related equipment and conditions.
2.
Mana ement Controls Assure that your management controls that are in effect provide for qualified technical and administrative reviews and approvals of temporary circuitry changes and temporary off-normal plant conditions.
This review should assure that the responsibilities and requirements associated with'the review and approval, installation, verification, removal, and subsequent testing of temporary circuitry changes and temporary off-normal plant conditions are clearly delineated in station procedures, are understood by the station staff, and are being properly implemented.
3.
Licensed 0 erator Performance Assure that management provides the necessary opportunities and time so that operators are adequately trained to carry out their assigned responsibilities.
In particular, confirm that shift crew members are provided special training for safety related activities that are infrequent, complex, or have unusual safety significance.
0 L'
If you have any questions concerning this request, please contact this office.
Attachment:
Vermont Yankee AO No. 73-31 Letter dated November 14, 1973 to the Directorate of Licensing, USAEC, Washington, D.C.
PZI~NONT TA.NEliF. NUQLIQABPQ~VKI:P~
01'T.'OK~A.TIO SEVI;NTY SCVEN O!ROVE STACLT RUTLAND, VI.".I(MQ NT 05701 VYV-3071 ALPLY TO:
P.
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DON I57 VEICNON, VERMONT OS;,54 November 14, 1973 Director Directorate of. Licensing United States Aton!ic Energy Commission Nashington, D.C.
20545
REFERENCE:
Operating
).icensc DPR-28 Docket No.
50-271 Abnormal Occurrence No. AO-73-31 Gentle!I!en:
As defined in Section 6.7.0.1 of th'c Tcchnical Sjiccifications for the Vcr!!iont Yanl:ec Nuclear Power Station, wc arc reporting thc following Abnormal Occurronco as A0-73-31.
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On November.
7, 1973, at 2101, while thc plant >>as in a shutdo>>n condition and whi.l'o the rcouircd Control Rod Friction tosting>>as being performed on control rod 26-23, a rcacto!!, scram occurred initiated by a high-high flux signal from tho Jntcrmodiatc Range Neutron Monitoring Sys t c!11.
An immediato invcsti.gation rcvealcd that r'ocl 30-23 was in the Sully withdr;I>>n position>>'hi'lc rod 26-23>>as being withdrawn'or its friction tost.')'his sit>>ation was a result of inadequate i!!!plcmontation of ad!I!inistratfivo or procedural controls and constituted a violation of Section 1, A. 8 of the Ycc)i>>ical Specifications Secti.on 14.5.3.2 of thc Vermont Yan);ce
):SAR deals with control rod withdra>>;Il errors
<<'hon thc reactor is at power lcvc1s below tho power range.
')'hc most sevorc case occurs when thc rcacto). is just critic'Il at room tcmpcrat>>rc and In oIIt-of-scq<!once rod i.s continuo>>sly>>ith<lr;Iwn,
')'hc results of those analyses indicate that no fuc)
<)a!;!ago will=occ!!r.
due to thc rod>>'ithdra>>'al.
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VERViC>NTYANICEC NUCLEAR POWFR CORPORA r!~.
)Jiroctorato of Licensing November 14, 1973 Page 2.
'I'ho station had boon in a pla))ned shutdo>>n condition since Sopto)nbor 28, 1973, in orclcr to porform core reconstitution and interconnection of the Advanced 0ff-Gas System.
On Hovembcr,7,
'973,
)'>ork had progressed to thc point where final core loading had been completed, At that point, it bccamo desirable to pcrfoian final core verification concurrent >>ith control rod timing and friction tests.
'In order to accomodatc both rcquiromonts, it >>'as necessary to instal 1 jumpers to thc refuel interlock portion of tho Reactor h)anual Control System in order to allo>> traversing of tho television camera mounted on t)ic fuel grapple>>hilc performing control
,rod friction and timing tests, Although thc intent of installing thc jumpers>>as reasonable ancl proper,. the ensuing implementation of this program>>ent beyond the scope of original intent.
'17)e reasons For this werc the inadequacy of intcrde)>artmental communications; in addition, certain procedures do;nonstratocl inadequacies, specifically AP 504, l,ifted Leads
- Log, OP 408, Control Rod Drive System,
- Further, the control rod friction testing>>as being performed in accordance 4'ith a Startup Tost Procedure; an approved operating procedure did not exist.
The result of the jumper installation 4'as a condition of interlocks 4'hich d3 d not prevent 4'ithdra>>al of )!!o3.c than one control 3.'od at a time.
Th c opera ting p(<rs onnc 1 <<'cre not. adoquate ly informed of'he jumpered interlock status; control rod testing 4 as rcsun)od concurrent >>ith core verification.
As control rod testing progressccl, rod 30-23 >>as inadvcrtantly loft in the fully withdra);n position.
After coro verification was complctcd, an<1 since the reactor operator 4';ls not cog!)izant that control rod 30-23 4'as still >>'ithdra);n, an adj accnt lateral control rod 26-23
)';as scloctcd and its conti))uous <<ith<lra>>al begun in preparation for thc friction test,.
)Jot>>'oen notch position 20 ancl 26, tho opc3 ator noti eccl rapid source range monitor res pons c
) )e innnodi ate ly init3 ate()
co))tro 1 rod insertion
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At the% time a f)ill rod scram
),"as in3 t3.atcd by thc inter)nc(li.atc range 1
monitor high-high flux si gn;!ls.
It.)'s 1:ltcr <lc!nons trated t;lat cont rol rod 30-23 digital position d).splay>>))s f>>nct3 oning p:opc.rly.
The reactor operator could not explain his Failure to observe th'c indlc. tlon of control ro<1 30- 23 bc3 ng fu]ly 4'3.thc)ra<<'n.
The 3)nn)ed i;)tc acti. on of thc Shift Sup(.)'vi! or on (l>>ty>> as to notify h3.gh or pl ant m;!n:l<<c)ncnt an<1 t(> doter)nine if po) s onno 1 )'(:rc on thc
). cfuc 13ng f1 oor du)'in g thc 1>> cidc>> t;u) cl to
) cqucst dosimeter 3 ();)<li))gs of a I 1 pcr: onl)<< I at that locat31 nn on thc cons('rv')t3 vc
)ss()}l)ptlon th))t a cr3 tie;)13 t} n):)y 1)avc occul )'c(l ~
)'1 vc p('rs onnc). 4'(')'e 0!1 th 0 ref>>(!I 3.n <'
I 003 )it the tl)!!c 3 n ()re<is not
)dj!cent to thcopcn vessel
'1'hc maxim>>n cln: 1) n>tcr rc ldi ng of th pcrs(I))nc) invol v(.'-d 4'lls
.> !1)'o'8()vc)', th) 5 tot(l] 4".ls l)ccu)')l)Ia!:e(l ovcl' five hol)3 4'o)'1; pc)'3 c)(l al)(l not:)t t)'il>ut:)l)lc to t))3>> inc'i <)ent,")lone.
It. 4'mls
- llso vc
- )'ifi c(l lh'lt th<: inc;11 l))'<<c) ):)nn3 to)'s,
! he co))t",.nl)ous lir )!)onl,tor 0:1 thc rcf>>c l.i;1!! fIoo)':ls 4'(:I 1;ls thc I!c;)ctnr fl>> i J <I in!!
<>Onti lat ) on l'.xhaust
)non;it c>).'s shn<<'(,<1 nn i,nc)'cas((l
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VERMONT YANI(EE NUCLEAR POWLB CORPOIRATIOi 1)ircctorate of Licensing Novcmbcr 14, 1973 Page 3
Folio>>'ing the arrival on site of the Assistant Plant Superintendent and the Reactor Engineer, further evaluation determined that the scope of installed jumpers was beyond thc original intent.
'l1)c julllpcrs werc removed and it, >>as decided to perform a subcriticality test on each of thc t>>'o involved control rods>>hich verified t)ici,r proper effectiveness.
Based upon thc above evaluations, it was detczinined that no fuel fai)ure had occurred and no radiation problem existed.
'I'he installed intcxlock jumpers were removed and a verification test conducted to determine t)iat the rod block interlock was restored.
On Novcmbcr 8, 1973, consi)ltation with off-site hig)icx managcmcnt and cnginccring personn'el resulted in the rc)I!oval of thc invo)ved fuel assemblies.from the core for. sippi.ng and visual inspection.
No evidence of 3eakage or visual degradation>>as observed:
The folio>>ing is a listing of the assemblics exa)nincd and their location:
Assembly Number Coze I.ocation VT 164*
K'T 171"'I'67 V'I'75 Vl'49 27-22 29-22 27-24 29-24 31-32 In additi.on, a two rod cxitical test was conducted utilizing control rods 30-23 and 26-23.
As a result of-this test, it was dctcrnincd t)iat with control rod 30-23 in the fully iiithdzawn position, critic lity was achieved>>hcn cont)ol rod 26-23 was with<lzl)>>)i to note)i 16.
'I'he film badges assigned to personnel nn thc refueling f3oor at t)ic time Cf t)ie incident >>crc.,cnt out fox processing.
'I'hc r(suits of thc bil()gc bca'l'llig ))cl)troll so))sing i)idic;itcd a toL()l of. 50 mr beta-ganl)!);):)nd zc)'o ncutzoii 0):))osurc
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Ihi.s total b:idge c):posiil'e>>'a'j. ace)i'))))late(1 ov("l' two day wor); ))erio<1.
'I')ic results of t)lc zc):.;)inin~ four badges indicated thllt t>>'0 I) ldgcs measiircd 20 mz bct')-ga)l))))a Qn<l t>>'0 ))edges
)!)c')sllred 0
)))1 bet a-ga)l))'>)a
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Subse<'Iuent c)lci));)Iion~ by Gc))eral ):.3cctric Co. verified criticality
- it note)l 16 o)l zod 26-23 with zod 30-?3 ful)y I;it)i<ll'I'I"li. I'll)'t)ic'l e:i)cul itl.oil by General I!)Cct)ic Co, dctcrmin<id. t)i:it >>'jth
)o<1 30-23 fully>>'ithdz:wli in7". AI',:))!<) h:l<l iv<1 23 b(:cn fully>>ithdr;)>>'n t))c cxccss )'e:)ctivlty>>'oi))d )i(ivc 1)ceil 0.!)7".; I.)i.
"'I')icsc )ssc))bl )cs wcz<) visually ins))<)etc<).
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VERMONTYANI<EE NUCLEAR POWER C<-)RPORA7!
Directorate of. Licensing November 14, 1973 Page 4
General Electric personnel with recognized compctcncy in thc area of core kinetics, and in particular control rod drop accidents, uncontrolled withdra>>al 3nci<lcnts, ctc.,
dicl a qualitative cvalu)tion of what transpired based on thc above statistical inform;)tion.
An estimate based upon many previous calculations of a similar nature, was that the bounding results werc as follows.
The peak fuel center linc tcmpcraturc would have incrcascd no morc than 500'1 and the peak clad tc)))peraturc would have'ncreased no morc than 50'F from thc starting conditions.
'I'hereforc, thc fuel center linc tc)!)peraturc was no higher. than SBS'F and thc peak clad temperature was no higher than 13S F.
Plant management has discussed at length with all involved personnel
,the significance of this inci.dent and stressed tl)c areas of inadequate personnel pcrfor;)ance.
- Further, a review has been
)))ade of thc past and present performance of the employees d3.rectly involved in this incident.
This <<ssessmcnt has determined that these employees are capabl<;, sincere, and conscientous and that every reasonable assurance exists th;)t they arc adequately qualified in all respects to continuo in their. present assigned job responsibilities.
Upon completion of. an inclepth evaluation of thc total inci.dent an<1 the val Lolls no>> apparent 3nadcquacics, it is conclud<.d th<lt no s3.nglllal'utstancling area>>'as predominant.
The Plant Opc.3.ations Rcvic>> Committee (PO)lC),
),;et to review the incident. and ma<le the following rcco))m)cnd;)tions <<nd/or concl))sions:
The original intent of the jumpers was reasonable; ho>>'cvcT, the final condition obtained was
- improper, and thc
)pplicd jumpc1's should have been removed i)m!)cd3.atcl>'ollowing thc completion of core verification.
2.
')'he results obtainc<l from,thc fuel <<ssc;!!blics sipped and inspected on >love)!bc) 8>
19'73, showed no obsclvcd 3ndic<!tio))s
>>'hich would pl'cc)udc plant stilrt))p.
')'hc P) ant. Opcrat3ons
)lcvi,cw Co)l)m3ttcc questioned whether adcou;)tc scnsitivit> to s3;>ping still <)misted c<)ns3dcrin<> thc clapscd shlltdown t3t!c <lnd )'ccoiil)PO!)dc() til)i1n lw0 known 10<))<<'3'8 pr<v)ously 1'clilovcd dt)13ng th3.s s))))t<lown a)id sil)l)ing to deter))!n<'. 3f a<tc)<lu<:tc scnsit3v3 t>'t3) 1 existed.
On lieve)!)))cr 11,
- 1073, two fuc) asscmbl3cs wc! 0 S3,)))<)<l in;)));)ttcmpt to ))rove 1 ';u)d 1
scnsL'".) vity.
'1'hc ))osit3vc res))its 0)itaincd vc)'l f>'hc;ldc'qu;)c>'f sipping scnsitiy3tics ob:<))'v<'.d oil )~ov<'.)!)bc)
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VERMONTYANKEE NUCI IMIR POWEIR CORI~ORAT)'irectorate of Licensing November 14, 1973 Page S
3.
Subcritical testing results of'he t>>o involved control rods and the management evaluation of: thc plant condition on November 7,
- 1973,
>>'crc dccmcd sufficient to permit further control rod friction testing folio>>ing t))c incident.
4.
Administrative Proccdurc AP 504 "Lifted Load Log" >>as not adhexed to.
Jumper installation was not recorded in thc general plant log.
S.
All plant procedures relating to control rod movement shall be modified to reflect interlock xequiremcnts imposed by ti)c reactor mode s>>'itch position, 6.
Specific operating procedures addressing control rod friction and settling test s shall. bc developed.
7.
'!'!)c present AP 504, Lifted Leads Log pro'ccdurc, is inadequate and a
PORC sub-co)).".)ittec has been appointed to review a>><l/or 1'cv1sc tl)c cu11'cnt pl'occdul'c
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8, Until thc above appointed PORC sub-co)nm3.ttee performs'ts.t:)sl;,
no install't3on of jl)'))pers or, lifted le )ds shall bc perfor)l!Cd on the circuitry associated
).ith thc Reactor Plotcction Systc))),
the Primary Contain sent Iso]ation S)'stem, any
!:CC S) stem, thc Reactor t!:u)ual Control S>stem and any refuel 5ntcrlock until approved by I'ORC.
9.
No further t>>o (2) rod critical.testing shall bc pcrfor))lcd on side b> si<lc rods.
10.
T))c folio),"ing items contributed to tl)c incident".
a.
A lack of dcf3.>>it3.0>>
o)l tl)c 3:ntcrf'lc3.>>g of rcspons3bilitics on an 3.>>ter(icj)art))lcnta 1
]cvcl
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b.
I ailurc h)'l;)nt supcrvi 'ion to exercise r3gorol).
skepticism relative to,".1)norm)l or i>>adcqu;)tc pla>>t con<lit;i.n>>s t));)t ar<
cncountcrcd.
c.
Opc1atol c3 ro3'
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l)ircctoratc of Licensing Novcmbcl 14>
1973 Page 6
VERMONT YAN!(EE NUCLEAR POWER CORPORA1!--
At thc rcqucst of thc h)anagcr of Operations, the nuclear Safety Audit and Review Committee mct in a special meeting on November.
14, 1973, to rcvic!v thc incident.
The NSAR returned thc following co!!clusions:
1.
No unrcvic>>cd safety question was involved.
2.
'I'hc health and safety of. the public and plant pcrsonncl
>>as not impaired.
3.
Thcrc is no undue ris); to the health and safety of thc public if thc plant'is started up and operated in accord >>'ith the proposed schedule.
Sincerely, VER)lONT YANKEE NUCI,EAR POI('Elk COIU'ORA'I'ION Pl ant Superintendent
ri
MEMO ROUTE SLlP Form AEC-93 (Rcu.!I(ay Id, 1947)
AECR( 0240 See me about this.
Note and return.
For concurrence.
For signature.
For action.
X For lnrormatlon.
TO (Name and unit)
RO Chief, FSSEB RO:HQ (5)
RO Files Central Hail 6 Files Regulatory Standaxds To (Name and unit)
Directorate of Licensing (13)
Regional Directors, (RO II, III, IV)
OGC To (Name and unit)
INITIALS DAT (3)
INITIALS DATE INI'TIALS REMARKS REMARKS REMARKS NIAGARA MOHAttlK NINE MILE POINT NUCLEAR POLAR STATION DN 50-220 AO 73-11-17 The above abnormal occurxence is forwarded for information.
Distribution will be made by this office to the PDR, Local PDR, NSIC, DTIE, and State Representatives.
DATE FRO an)e>and unit)~
J. Brunner Region I REMARKS PHONE HO.
DATE 8-337-1246 ll/28/73 DSE OTHER SIDE FOR ADDITIONALREMARKS CPO I ISSI 0 SIS ~ ISS
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TO; IIII, JE!':ES I'. O'PEILLY - USIIEC - KIIIS OF PIIUSSN, II.
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PEBllUIS - STl SUI'EOIIITEIIOEIIT - IIEIIE PIILEIT I.'I LQ.-,", OF OFF SITE PO';tER
<.,-.-,.=.iJN,T TO TECffffICAL SPECIFICATIOilS 1.'t3 d AND 3.6.3, HE ARE REPOBIffG ri'DtfOW'.,'L OCCURREffCE HHICff h%S TELEPHOHEO TO YOUR OFFICE OH 'l'l/'l8/73 AT APPROXIt'NELY 1030 lfRS.
Ofl ffOVEfBER 17> 1973 AT 'f626 lfRS., HOfE NILE POItlT ffUCLDiR STATIONS UlfIT 0'1 LIffE.
A nCACTOR SCfV.H OCCURRED 6.4 SECO;tOS ttATER AS HC SETS 3~131 IVN 14'l UPON LOSS. OF POKER lfiRE COASTlf(G 00WH Af'0 TRIPPE0 AY 55 ffZ.
MITfkIfk 9 SECONDS FRY THE LO"S OF ALl. A.e., TllE WO DIESEL GCf~EVTOB SYSTB)S HERE. UP N<0 HAD 0/ERGIZEO TttE Ti0 CONTROL ROD DRIVE PUl',PS TO Hf>IffTAIffl.EVEL.
REACTOR HATN LEVEL HEVER DECREASED, lVrfD NtS t@Itf-TAIffi0 l'ITHIH TfK ff0Ãf< EXPECTEO RANGE FOR THIS TRMSIEHT.
ALL SYSTEr5 FufXTIOtfEO AS DE,"IAtf"D i'ITH A LOSS OF 115 KV WITHOUT TfkE TURBIHE-GEflERATOR UHIT AVAILABLE.
Tflf: 115 VV LIffE VAS AUTO'VG'ICALLY RESTOREO TO SERVICE IH APPROKIfNYELY ~o SECO"DS THE REACTOR l%S RESTARTEO AT APPROXIMATELY 9 NfD ffOR'NL CO?fDITIOlfS ESTMLIShEO ftITHIffTflE Ptf AFTER RESTOfNTIOH OF DOnt 11S VV LIhES PLA'n.
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'EXPEP.IDi'CEO A LOSS OF ALL OFF SITE PO'<E'ER.
FOLLOHIttG OPERftTOR CRITICAL DEVA)NSTPATIOHS, THE REACTOR HAS IH THE JUST CRITICAL COf>DITIOll, II'!>E SWITCH IH START-UP flODEMTOR 'fEHPERNURF. 2Q7'F, HITtf Oi'E 1 f5 KV RE~LAVE Llt>E DE-L'l',t'.RGIZED TO CONNECT TfkE 115 flV LIflE TO JAFHPP.
IH THE COURSE OF TffE RCLA( 'hORfi ASSOCI<'iTED HITff TllIS COhtfECTIOt)y A PUsf)T ELECTRICIAH 85'IPED 6O FDS/
SEAL If( K'LAY, l'O'TCff TfuPPEO AfS OE-CE'iEROIKED HEtJ~Y 94.". CAUSltfG TftE LOS OF THE RBSIffIlf" TffOmS Z.
r Eaf:rnS STf(TIOH SUPERIHTf:.ffDFffT HIHE Hlt.E POINT ffUCLEAR STATION
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4e MEMO ROUTE SLIP Form hEC-93 (Rcu. ) (ay l4, l9d7) hECM 0240 See mo about this.
Note and return, For concurrence.
For slcnature.
For action.
For Information.
To (Name and unit)
RO Chief, FS&EB RO:HQ (5)
RO Files Central Nail & Files Regulatory Standards INITIAIS DA (3)
REMARKS NINE NILE POINT NUCLEAR PQKR STATION DN 50-220 AO 73-11-20 To (Name and unit)
Directorate of Licensing (13)
Regional Directors, (RO II, III, IV)
OGC To (Name and unit)
INITIALS DATE INITIALS REMARKS by this office to the PDR, Local PDR, NSIC, DTIE, and State rePresentatives REMARKS The above abnormal occurrence is forwarded for information.
Distribution will be made DATE FROM (Name and unit)
REMARKS PHONE HO.jj~
DATE
-337-1246 11/28/73 USE OTHER SIDE FOR ADDITIONAE REMARKS GPO r Seri 0 sss ssa
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FOUND TO JJE i'USZ~IOHQJJ AT THE 02 407CH M."XTXGH.
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DQIVFi8 g)Fi gFiFiif )fist)lfr$0 F<)P. QVKPlfAUL DURIiifG TJE KXT KHJLfiJ i'3 oui'JiACK, iJARCJI J 97 m a TJIE 0 'rJPdiTOPi VERXFXE0 THAT HEUTraob'J DHSTRUI'Si'$~ATTO>f A HXQffLY PJECRXTXML REACTOR PPY'f fJZTH ZNoy PAJ)o J
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MEMO ROUTE SLlP Form AEC-95 (Resu h(a) 14, 19d7) AEChf 02(0 See me about thlt, Note and return.
For concurrence.
For $IEnature.
For action.
For Information.
TO (Name and unit)
RO Chief FS&EB RO:HQ (5)
RO Files OGC Central lfail & Files To (Name and unit)
Regulatory Standards Directorate of Licensing (13)
Regional Directors (RO II, III, IU)
TO (Namo and unit)
INITIALS INITIALS (3)
DATE INITIALS REMARKS REMARKS REMARKS NINE NILE POINT NUCLEAR STATION AO 73-11-13 The above abnormal occurrence is forwarded for information.
Distribution villbe made
\\
by this office to the PDR, Local PDR,
- NSIC, DTIE, and state representatives.
DATE pp,/~~/
E. J. Brunner Region I REMARKS PHONE HOs DATE 8/337/1246 11/16/73 IISE OTHER SIDE FOR ADDITIONALREMARKS GPO S tet I 0
<4$ 4//i
1
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}f1.}'lf Pygfft}CPL 53 C1FIQ T1'Qj!5 i )3 d Af!D 5PLCi f it.'ATJQlf:
SPECIF1CATIQh 3.6.3 d
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ALL flCACYOR Of Ef}liH8 <.'O}fI l}IOI)8 P>XEf 7 COLL} sffUYUOHt), 'rt': f<c StIt'LL t!OpVp<l,tY f<~ (0'QI)p~f,p $00 ))5 1!},'f~T)Rt!Al, t,IHFy Tt,O DJE3p, Pgt!ERATQR PQ':]ER TEt~
N!0 T40 Bl"T"ERY.'f',t'S...
t A l-;h&UttO'C<.'}Nf'.Eu Of< THL' v~:ECQh'DA@
OF 10>s fI,ESEN<E POPER TRA',ts-",OfLR M(!0kkIH6 Tr<Att5FEr< QF LOAD TQ }Ntt. J'.t!P THF, REttO(>AL OF,
}iffy Tr<AHyFARMFr( FR@>>.pgRvkcE AT IMO "OU}"5 Olt
'< ij'Qj'73.
ttOTtl t'l" t;tf Lit!E5 ffE'R<": ()PERABLK AS 4ER}=.,',5F; T40 DIESEL GEH-O'NOf;:Y-;YEtls. te/E,ct'rHt t:E:EB'E 'fktut~FOMKk,PONIES N ItlYLYNL f AR'f Of'ffE
)i';~ RE5CR<VE PI~ER 5V5TEt, Fon nr>>E V~ia"= PQlffT UHIT 1 N!D THOS Qt!E QF
}HESE TWO SYSTE":
wAS Ittbp@AaLE wI}v Tt;O'Et,'O':AL QF tG>: 'r@,SFdhKf,.
sVbsEl}Uf'.tA'ff},'NIOAT10hSNOWED E~. 6OO VOLf f)If}L'graf'LYIHl,"j)K [)ttg )fEfj<LR, ht;P(y<S 9(/F.
PHARg OF T)fF, RPC9)!DARY OF THE 7fiRl!5FrJ}<l'tER~
TflE HIRE ill6 REf)RED AfS }ffL'fRiSFORH}R PLKLO t}t'<CK itt SFR~ ICE 37'l3 ffQUR5 'fI/~3/73.
Pir<-~Lf> UPO!f TfK MCT Tffl<T if-'0 Di}'it 4 Gf t!EtNTOR'ERE AVl<ILABLEAs ltELL AS Oi(E )l~L fN RL'~'t."L f'O'ALf'. 8Y"7Eh HO l)1rHCtKt'MLS f.'OltLD I'Qf:, f/FPf OfcOUt!TFRED HAD THEsE ""5TEl'"
BEEt! RE!1UJRED FOR QPEBT~QH-THEREFQRf',
HQ ffr}zAR0 fN'REsf:HTED To TffE GKt!ERAL PUflLlc DURittG TifF. TittE
'tOv~eg T5~ffcit'{)Rt)FR gsAS PFty~~r/)tED PRg) SERVICE.
T. J.
Pt:Reit!5 STATIQtc 5UPERIll } Et!DEt!T ttIQQ PAIt!T I(tlCLQAR STATIOH
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J Cs MEMO ROUTE SLlP Form hEC-D3 (Rcv. hfay I4, ID47) AEChf DEED See me about tnls.
Note and return.
For concurrence.
For slcnature.
For action.
For Inrormatlon, TO (Name and unit)
RO:Chief FS&EB RO:HQ (5)
RO Files Central Hail & Files INITIALS AO-73-11-10 NIAGARA HOHAMK - NINE NILE 'POINT DN-50-220 To (Name and unit)
Regulatory Standards Directorate of Licensing (13)
Regional Directors RO II TTI IV To (Name and unit)
INITIALS (3)
DATE
'INITIALS REMARKS The above AO is forwarded for information.
Distribution will be made by this office to th PDR9 Local PDR, NSIC, DTIE, and State REMARKS Representatives.
DATE FRO
(
me nd unit)
E. J. Brunner RO:I REMARKS PRONE NO.
DATE
-337-1246 ll/13/73 USE OTHER SIDE FOR ADDITIONALREMARKS OPO s Ie'll 0 S ~ 9 ~ SS9 P
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~ AOHOPJSL OCCl)PPFttCF, 73 't't-'t9 FAILURF. Ot" O'tL'OH LOW LD'kL SBiSOR DURING ROUTINE SURVEILI ANCE Tg"-TING ON 11
'Ig 73 RT 1509 HOURS OtiE OF TAO 14STRUiW[NT CHA."l,"lELS LES FOUtlD TO RCTNTC RBOVL tmp'SL SET POINT, BUT HITHIH THE ALLOeBLE RANGE OF TABLE 3.6,2 QF TECHNICAL SPKC7FJVTION.
HO'llF)ER FOLLOHIt/6 0 RtYIL'0 ON 10(12/73 -'t0!lMY -
OF TtlE SURVEILLN)<CE TESTI)N, IT NS NOTED THAT IN THE BASES OF Tgg $)PP)kgb SPECLFTNTIOl)p TttE jjtgRUHEti7 @8 8EYDt'j!) 0 S t'lORHAL DEYIATIQ<'li THERE FOJ,,E~,RS;:DEFINED Iu TECHNICAL SPKIFICNIONS l.lX, NE PRE PEPOPTIH6 AS Att MN08HAL OCCURRF'HCE THE FRILURF. OF Ol'E LOW LOP. LEYEL SEttSOR.
'fECHHICAL SPECIFICATIQH 3.6.2 (f POTt:CTV)E ItjM'PUHKtAATIOH)S'rA'rES:
"'NE SET VblttTS, mHIVut< nUt',BER OF TRIP SYSyEy<S, g/0 hIHIl-*,UH NUhBER QF 7h'STREE.tyfg gygygg.~ THAT higg gi OPFPR~Lg Fgg Pgg Pggtyyo'~
OF REACTOR %DE 54ITGH SHALL BE AS GIVEN l'Vi TNLE5 3.6.2a TO 3.6.8$.
PN< i~TER t,CFM Lml REACTDR N<XL'R Lc YL'L t'<IttIt<U<"t HO. Of TRIPPED NIHIHU<t tlO. OF'PEMLE SET POIttT DEYNTIRf OP OPPPPPLE tP>P
- .'lt,g-hjlt-;".HY CtN44ELS Pg 5YSTEHS OPEVEBLK TRIP 5YSTEH
<<5 ft. })Q10H e(n(i",alii nmmH Web-'r 1evd
. THE REAt:mR. LOu LO.'N.TER LEVEL SEl<SORS (2
EACH VE8, 'rhlP CHA'lVEL) ~;ERE ROuTIHELY TE'TFP.
PEOPt3 N"'ovttP m ACTÃTE AT 4'" Nt,orat t'IHtt")H HOPIS. tWKP t,.FIDEL.
KTVATIOH IS 5'" BELOW tlIHINlHttONA'L g.6".
SYSTEi" r
vht.,"AP,'f CO~LLttT ISOLA'tImt CG.'cTAiHHEl>T.ISOLA XQH rVL'RGL'llCV MiitlCii.'.
' r Oli START COK SPRAY PUMPS P SD/SOBS PER 'PIP CHNt>)FL
) SVtSOk PER TRIV EHAllHEL TO IllITIATF.
<<Era<<PS gjlJ) D CQU5E REOU1RcD FUHCTIOii AT 5 FT BELOM Hlu, lJORV"L LEYEL It>ITIliTES CQ!lTAItNEtiT SPRAY Z SEf]SORS PER ONNHEL t
ONE SENSOR PEP TRIP CHNtttEL TO PARTIALLY INITIATE)
ALSO HEED HIGH btA'HELL r RESSuRC MOULO CAUSE RE(UIREO FUNCTION AT 5 FT.
BELD'A Ht1).
NORMAL LE.VEL Qll) 3,5 PSI
~0 La h
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~FgggOPy
)u d, 0 lit:ltM
~0.
ee ALL YVF SYSTP5 LISTED ABOVt; MOULD FUHGTKOH AT THE REqUIRED SET PorffT THE l.HAf(f<EL I
]2 TRIP 4QULD OCCUR AT 0'" BFf.gM HIffIHU"1 NOBEL AHO THE CHANt/EL 'l'f TRIP MOULD OCCUR AT 5't;LOW HIffIÃti'fhoNNL (f<CTNiTIf'ft'HE PROTECTIYE FUCTIOH).
BOTH TREP CHAftHELS NS'f luH';YESO'" 70 Oil'rAIH THE l'Ro'tFC'0".VE FUHCTIGH ANP EYEtl IF Ttll: 18 TRIP CHNlNl-FUffCTIDh OCCUR".-
.';T!ST, THE "YSTPf PPOTgCTJg>
Fg CTIOH AULD hOT OCCUR
..~M'/f. THE 'f'f TRIP SYSTEM MTtgTFD.
TESTING OF ALL
.'gHSOPS IN Tt)I"- gfiQY, Sgj'~t:.D )!AP'Ng PPQTFCTIub FtJHCTJQff HQULD BE 7HITIATEO AT THE OE:>RED LEAL (S'ELOu ffItfif~uOrw>z).
rSE rN."Tf,u";rffT. mO."O, aV RCCALIBVTEO N,D YERiFIift TO OPiRATE AT THE 5'EI.O'.! HINIhdH HOARD SET Polfll.,
BASED G f THE MO'K, HO UHWE, SIif'ETY fNZARO WPS PRKSEf')TED TO THE GEHEPAL PUBLIC NOR uOUZO tuiV:>'.ra a-OtJIMb yo FUHOI0l< FAIL'0 FuNCYION PROPERLy AT ITS PEglIPED V
SFT.
P~ANT.
'ifL'S:Ir~TIWS hVC FO>ffD If'HE BASES OF THE 'rECHflkQL SPECIFICA7MN 3.6.P MC ARr t<OT l'Af'A'F 'l'l/l. YAbLK l'. ALL%MR BURT GEHEPAL SUPERIHTH/0"-ViT
><.W<Vv SV<SVT>i>ft HING HOYLE f OIN'r NUCLEAR SN'rkOH
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TO (Nant ~ and unit)
, A" H.'D. Thornburp,
- Chief, FS'&EH IHIIIAUI DATE REMARKS Licensee:
Niagara Mohaw Power Corp.
Docket No.:
50-220 '
Abnormal Occurrence.
Facsimile Message received I
TO (Mama and unit)
IIIITIALS REMARKS ore ower x.s rx-
~* bution fue1 bundle se ents found RO: jIQ (5)
DR Central Files (1)
Regulatory Standards Dir. of. Licensing (13 TO (Namo and unit)
RO Files Central Bail & Files FROM (Mama andunlt) fi; R. T.. Garison,. Chief
'gacility Operations
' Branch DATE 8/30/73 DATE 3)
ItttTIAIS
~
~
The attached report from the sub ect licensee is forwarded in accordance with RO Manual Cha()ter 1000.
REMARKS The action taken by the licensee is considered appropriate.
'Followup will be performed durin the next inspection as a
ro riate.'o iesiof the report have been forwarded to the PDR, Local
- PDR, NSXC, DTXE and State representatives.
The licensee will submit a 10 day written report to Licensing, USE OTIIER SIDE FOR ADDITIOKALRF MARKS CN I Ittt 0 (0-c:
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tm. VRIES P. O'RF;ILI.Y FROH; HR. YlIHAS 3. PNKlHS l/IHE MILE POINT NUCLEAR STATION DOCfX'f t(0. S0.220 On or about l600 hours, Auqust 29, l973 FolloMIng a MUf,ice Gal'the'ation 5f 548 Ldc0$ por R40ge Nonftbrs (LPR/) and gobqequent cqre power digttfbvtiqn qelrv1yt)qn foe'I bundle sey~enL'".. were found to be operating slightlv fn excess of the allowable Qvolago planar'IIGHT as sh6ttn gn Fjgut'0 3.).1 The Fuel Bundleg irr g&estÃan mfa re)god l type, The vkzlrPQQ ovN'yqe plow@.'%R mw found to ba approximately l075 Qk/FT.
For th{s Fuel type and nodal exposure oC approximately
$ 9% %0/ST tho limit shown on F)gure 3.1.7
$ s approxiootely l0.6 KH/PT. bldtatelg steps pro taken to <educe. the maximum average planat'H9HR by rqdoring Cqv'e The~) pq~t qggng Reyqtgt Pecireolytjon F~ow, Svbseqvent core power distributions calculat)ons shnwed all fuel types to be oporating Mithtn the limpet". skoMn on F)guro 3.1.7.
In ordel'o Nh)0th)n thh Cot'e po'd 54t;v)butfon jnpqt, diha (LPRH) re>~ahU<ty et
- e. h)gh 'level the frequency of t.PAN ca)$ bret$ ons C'fl be
'ncreasod f eo the nom)nal Full polar <anth Aequency to every Full power two tRQk pc)')od.
In eddiHon> steps wfll be taken t0. a)ter the existing rod pattern tq vqhefve a flattet Iemr dfstHbution which will )mpmvo tho mwq3n between ope~tAng )eve'fg end limits,
Mt:<<F.'OUTE SL.
"'fornt AIX-III(Itch. i>lay I4, IOIT) hlX.M 02do Soo tno about thl5, NOta and roturn, Foi honcurronce.
For srcnature.
PQ -o2~
For act)on.
For Information.
TO (Namoandunlt)
H.
D. Thornburg, Chic FS&EBI RO TO (Name and untt) cc:
RO Piles
~P Central File INITIALS DATE INITIALS DATE REMARKS BLUE SHEET NXAGARA MOHAVK POWER CORP.
(%1P-1)
Xb~J; d
e sheet is forwarded for t
Toses onl with the knowled e that REMARKS a decision was made b
RO:H not to issue it.
TO (Name and unit)
INITIALS REMARKS DATE FFTOM (Namo and unit)
REMARKS R. T. Carlson, RO:I PIIONE NO.
DATE 6/14/73 USE OTIIER SIDE FOR ADDITIONALREMARKS GPO 1 IOTI 0 eeS ~ <So IT I
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4 y I D. Thornburg,
- Chief, FS&LB, RO R..T; Chrlson, RO:I 6/12/73
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DIRECTORATE OF REGUt>STORY OPERATIONS NOTXFICATION OF A:1 INCIDENT OR OCCURRENCE Facility:
Nia ara
':mohawk Power Cor oration (Nine !file Point 1
Probl'em:
I
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It'ime of occurrence 8:08 a.m.,
6/12/73.
RO Region I (Newark) was informed by the licensee by telephone on June 12, 1973, that during planned surveillance testing of 'the pressure vessel electromatic relief valves at 12K of 'rated
- power, one of the valves failed to reseat.
The main steam bypass valves were open at the time, thus enablihg reactor pressure to be maintained
-relatively constant at 950 psig throughout the 43 minute period of steam release o the torus, which was terminated by closure of a manual block valve.
The followin; reliminary information was provided by the licensee:
2.
12,200 gallons of water were dumped to the torus during the incident.
3.
Hater level in the reactor pressure vessel was normal throughout the
, occurrence.
~ 4, I
No safety equipment was called upon to function.
5.
No radioactivity was released to the environment.
Action:
\\
1.
The relief valve is being disassembled to investigate the cause of failure.
2.
The licensee will submit 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 10 day written report:s as required by the Technical Specifications.
3.
The Region I (Newar'k) office is following closely the licensee's invest:igation Further action by RO, including generic considerations, will be based on de-velopments.
V T
4.
The Northeast office 'of the Office of Information Services and the State of
'. Y. have been informed of this occurrence.
The Technical Assistants to the Commissioners and the St:aff of the JCAE are beinf informed by copy of this notification.
/
(Further informat:ion on individuals to contact and distribution are to be prepare" by RO:}iQ.)
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t'IEMO ROUTE SLIP
)'orbu hl ('-b) I I ltm. 'btae I I. I') I I hl ( SI tl) IO Sce me about ttblt.
Nntn and rrbern, F or concurIbence.
b For slCnaturr.'or action.
For Inrormatlnn.
TO (I(arne and unbt)
D. Thornburg,
- Chief, FS&EB TO (Mama and unbu trbltIALS DATE INITIALS REMARKS I
Licensee:
Niagara Mohawk Power Corporation Docket No.:
50-220 Abnormal Occurrence:
TlJX dated 6/12/73 REMARKS RO:11Q (5)
PF Central Files (1)
Regulatory Standards'ir.
of Licensing (13 TO (Name and unit)
RO Files DATE INITIALS The attached report from the sub ect licensee is forwarded in accordance with RO Manual Chaoter
- 1000, REMARKS The action taken by the licensee is considered appropriate.
Followup mill be performed durin Fbborb( NO DATE 6/14/73 F IIOM (ttame and unit)
~ i C:."'
r R. T. Carlson, RO:I REMARKS the next inspection as a
ro riate.
Co ies of the report have been forwarded to the PDR, Local
- PDR, NSXC, DTIE and State representatives.
The licensee will submit a 10 day written report to Licensing.
USE OTIIER SIDE FOR ADDITIONALREMARKS GPO t IS)I 0 ett 0
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NKA4<4(1842) (2 09654$ E'f@) PQ 06/'f2/7$
TCS IPHNTZZ CSP G
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$ 15$ 422049 TOMT OS<(EGO NY 19$ 06-)2 06g~P EST PMS KEE YOUNG~ TLX 0
CARE ATOMIC ENERGY COMMISSION DIVISION OF REACTIVE COMPLIANCE REGION
~ 970 BROAD ST NEVARK NJ REACTOR OPERATING AT ~2'ERCE'NT P04~ER VITH $ 0 PERCFNT BYPASSED STEA< ('l00 PERCE'NT BYPASS EQUALS 40 PERCENT TOTAL STEAM)o RE'ACTOR PSIG 950'ORUS TE'MPE'RATURE 75 DEGRE'ES F
TORUS LEVEL go2'EET SUBMERGENCEo TESTING OF ELECTROMATIC RELIEF VALVES IN PROGRESSo ALL VALVES HAD RESPONDED SATISFACTORILY UP TO THIS TTNEo OPENED FIFTH VALVE OF SIX (11$ )
AT ORO<
HOURS INDTCATEO BYPASS STEAN DROPPEO TO 'l6 PERCENT.
ELECTRONATIC VALVE SMITCH THEN CLOSED
{DURATION OF CYCl E 1 ~ $2 SECONDS)
BYPASS INDICATION RENAINEO AT l6 PERCFNT TORUS TENPERATURE'TARTED SLIGHT INCREASE TERMINATION UgfI +ALII
~~ II II fl OF ELECTROMATTC OPE'RATION BY CLOSING MANUAL BLOCKING VALVE UPSTREAM OF 1 1$
ELECTRONAT ICo BYPASS VALVE POSITION RETURNED TO 27 PERCENT (REACTOR SHUT DOVN HAD BEGUN DURING ELECTRONATIC VALVE 1'ly OPERATION, THEREFORE DIFFERENCE TN STARTING ANO E'NDTNG BYPASS POSITION)
TORUS TEMPERATURE HE'AT AT l25 'DE'GREES F p LEVE'L AT $ o 6 FfET SUBMERGENC Ea REACTOR PERAMETERS UNCHANGED QURI NG I NCT OENTa CALCULATED MAXIMUM BLOMOOVN OF COOLANT 25q000 GALLONS'PPROXTNATELY 207 K POUNDS OF STEAMo DURATION OF ELECTROMATTC OPERATTON 4$
NTNUTESo REACTOR ORDE'RLY SHUT DO>JN COMPLETED TO LESS THAN 110 PSIG AT 1/00 HOURSo TORUS COOLANT ACTIVT'TY INCR'EASED FROM 470 C/M/NL TO 5u6 C/M/ML DURING INCIDENT, WRITTEN REPORT TO FOLLOV BY JUNE T J PERKINS 9 NILE POINT NUCLEAR POtttER STATION
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