ML20024G164
| ML20024G164 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/04/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20024G153 | List: |
| References | |
| NUDOCS 9102070617 | |
| Download: ML20024G164 (8) | |
Text
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FCOTT 10. 50-20 1
NOETi!LTI: S7A7ES IGI.F CC(TAhY PUI77 OT FIOl<GFD ISSUANCE OF M'I2DD.T
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7C PTOVISICIAL OPETATIK LICDEP
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Tne U. E. Nuclect Ibguletory Corcission (the Conniccion) is concidering -
insuance of arendront to Provisional Cperating License No. DPR-22 issued to the Northern States Power Conpany (the licensee) for operation of the
. Nonticello ime]ce.r rencreting Plent (the facility), a boilino-vater recetor locatc6. in tricht County, Finnesota.
Ihc amendment would revise the Technical' Specifications to (1) eM recuircrente tbst w u]3 lirit th period of tim operation een be continued vitb frrnv#k centrel reir tht ecuV beve control' rod drive recher' int-col]c t bemjr-f ri2 ores m:~ (2) receire increared control rod curveillance when tbc resritility of a control rod drive rechanism collet housing failure C7ict:.
Prict to issuance of the proposed license amendment, the Cenu:ission t.
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. will have ret the firv"inos recuired by the Atomic Eneroy Act of 3 954, cc arcrY (t_x i et) c:v' the Corriccien's rulce en6 regulatione.
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, the licensee mcy fi]c a request for a huring and any rerson shcEc interest ney te affected by this proceedino tray file a rmet fer c becrine in the ferr cf a mtition for Jeeve to intervene OFFlCE >
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Form AEC-318 (Rev. 9-53) AECM 0240 o u.s.a u. w r r
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witi rccrect tc th( ist.,uen& of the arencrent tc the subject fecility eterttinc licence.
Petitions for leave to intervene rust be filed urder orth er t.ffirrctice ir acccrdancc with the previciens of Section. 2.7.14 cf J r r_ r' Ir r t. c f the Com:Jt ricr 'c reculcticrc. 1 t etitico fer 1(z.vt tc intervena muct eet forth the interert of the petitioner in the proceeding, how the,t interect may be affected by the results of the proceeding, and the retitioncr'c contentions with respect to the prorosed licensino ection.
Such rrtitiere rect N filer in eccerfence with the crovicionr of this TErIIII. ITCI!TII noticr erd Section 2.714, ard must be flied with the lecrettrv cf the Cctrcirzien, I;. E. IbclePr Feculetory Ccmtirsion, is. 'ir^rcr, I. P.
2(DE, Attentien:
Iceketin7 cre Scrvice Sectict, M*
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/ cr w of the retition ent/cr re vect for c hetrinc cherF Fe cent tc the hecutiw Ieoal I'irecter, U. E. I uclear Jeculatory Certicion, W ir - tc,, '. C.
- U'..., an' tc Cert.36 CM rnoff, Es~rirt of Shaw, Titt r,
Fottc an6 Trc@rideo, 910 - 17th Street, N.
U., Kachington, D. C.
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or licenru..
"cHficr 'cr In vr tc intr.rvnrr turt 5: ccccrerried bv e run Trtirg rf fi,"vir stic' icentifice the rWcific espect er erectr of the prceec? ire cr te 5:hict' interventien ir deEirco anf EDecifies with pSrticultrity the fack c Wici the retitioner relies er to Loth hin inttreat en? bit conterticrr 5:ith rectrC to rech ermet on which intervention is recucctcf.
Irtitiere rtz ting contentions reltting only to rzttx ts outsife the Comiscien's ivris'ictier till rt 6:rio'.
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All retitions will tw acted upon by the Cennission or licensino board, r.
decicratce' by the Comission or by the Chairran of the Atomic Safety and Licensine Ecard Ennel. Tirely petitions will te considered tc determine i:1 h
vbether a hearing r.nould te noticed or another appropriate order iscued keppg Y:
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regarding the disposition of the petitions.
In the event thet e heering is held and a perscri is permitted to e
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ir.tcrvenc, he lveorer, e party to the proceedina and has a richt to E@B t.
$p participate fully in the conduct of the hearing.i{ par exanple, he aury.
O r>re&nt evidence and cratine and crose-examine witnesres.
For further &tailc with respect to this action, see the Cormincion'r o
letter to the Northern Steter Twer Cocpany dated Septerter 24, 1975, and the ettached promsed Technical Specifications ard the Gafety Evaluation by the Cculesien's ettff dated Septerber 24, 1975, and the Ibrthern Statec rwer p
Ceeperty's letter dated October 14, 1975, which are availahle for public- _
i inspection at the Cocrission's rublic Document Room,1717 H Street, M. W.,
Uethincton, D. C. anS at Tbc Envircrmantal Conservation Library, Minncepclis 9
Q Public Litrary, 300 Nicollet Pell, Finneapolis, Finnesota 55401, The license
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rrendncnt aM tbc Safety Evaluation rey be irmpected at the reove locations, trf r com r ry b obtained mon recuest e& rested tc the U. S. Imclear Itculetory Corniction, varhirston, L. C.
20555, Attention: Director, Livieion cf I(ccter Licencinc.
DEC 0 975 Dated et Ectber&, NrvlaM, this KE T!C 10CIIAR FIGUIAKRY COMMISSION n" - cin31 S!cn?d W :
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k nnis L. Ziemann, Chief Operatino Deactors Dranch #2 1.ivj rler rf I'occter Licenrirc
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w 10FUEUS CA71E RUITL CCfIPMil' COCF17 IC. --50-20 t'UCCELLOTUCIEAR GEt:ETATI!C PING PRGOCED AMEhTMEIR 'IO PEOVISIO'AL OPETATItG LIC_ ENS.E.
l Amendrent No.
License No. DPR-22 1
1.
The Nuclear Feculatory Comission (the Coartission) has found-that:
1.
7here ir reereneMe ersurance (1) that the activities authorite by this arencment can be curriucted without endereering the -
-health and cafety of the public, ano (ii) that such activities will be conducted in compliana with the Comission's regulations; P.
The irceence of thic arendent vill not be inimicci to the cc:rce 6crenne an5 security or to the hecith an5 cafcty of the public.
t 2.
i<cerdincly, the licens.c ir arenfed by a chance to the Uechnical Fpecificaticrr cc in?icrte? in the ettt: brent to thir licente acendeent and Paraoreph 3.P of Fecility Iicense No. DPK-22 -is hereby arended to rced rz. fo1]w:::
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7echnicc1 Srecifications Ute Technical @gificatiens contained in AroendiF E, et revised, ere hereby incorporated in the licence.
Tbc IJccrsee chall operate the facility.In accordance -
. with tnc 7cchnicc1 Epecifications, es revised by.
issued chanoce thereto through Chance 14.
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7hir licente enendrent in effective as of the date of-its issuance.
EU TE !CCIJL FJ.E1/SCT1 CCM ISICi t
Err] h. Cc11er, Arcistant Director for Cperating Feactors rivicico of Reactor Licensino.
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Form AEC-318 (Rev. 9-53) AECM 0240 yu...oomm,......or,,u.
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ATTACIP"fNT TO PRol>0 SED LICENSE A'!ENEMENT PROPOSED Cl!ANGE TO THE TECHNICAL SPECIFICATI0::S PROVISIONAL OPERATING I.ICENSE NO. DPR-22 DOCEET NO. 50-263 Delete existing pages 76 and 63 of the Technical Specifications and insert the attached revised pages 76 and 83.
The changed areas on the revised pages are shoen by marginal lines.
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3.0-LIMITED CONDITIONS FOR OPERATION.
4.0 SURVEILLANCE REQUIRE.A*ENTS 2.
Reactivity margin - stuck cont rol 2.
Reactivity margin - stuck control -
rods.
rods.
Control rod drives which cannot be moved 'with cont rol rod drive Each partially or fully withdrawn pressure shall be considered in-operabic control rod shall be. exer-oj. crab l e.
The directional control cised one notch at least once each week. This test shall be perforced valves for inoper:Gle control rods i
shall be disarmed electrically and at.least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the i
the rods shall be in such positions event-power operation is continuing s
J that Specification 3.3.A.1 is met, with two or more inoperabic control l
If more than six non-fully inserted rods rods or. in the event power operation are inoperable during power operation is continuing with one fu:1y or the reactor shall be placed in a shut-partially withdrawn rod which cannot be moved and for which control rod down condition.
If a partially or fully wi'hdrawn control rod drive drive mechanism damage has not been ruled out.
' Die surveillance need not cannot b moved with drive or scram be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the pressure the reactor shall be brought, to a shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> number of inoperable rods has been unless investigation demonstrates that reduced to less than two and if it has the cause of the failure is not due been demonstrated that control rod drir to a failed control rod drive mechanism mechanism collet housing fai)Lre is not collet housing.
the cause of an immovable control rod.
B.
Control Rod Withdrawal B.
Control Rod Withdrawal 1.
Each control rod shall be coupled 1.
The coupling integrity shall be
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to its drive or completely inserted and the directional control valves verified for each withdrawn control rod as follows:
disarmed electrically. This require-ment does not apply when removing a (a) when the rod is fully withdrawn control rod drive for inspection as long as the reactor is in the refuel-the first time subsequent to ing mode.
each refueling outage, observe that the drive does not go to the overtravel position; and T.3/4.5-2 76-
A-Bases Continued y nnd 4.3:
with drive pressure.
If the red in fully insert ed and then disarmed electricallv*
in a safe pr ition. of maximum cont ri.bution tc shutdewn reactivity.
it is If it 'is disarmed -
electrically in a non-fully shutdown reactivity limitation stated in Specification 3.3.All.insertcd position, that position shall be can be shutdmn at all This assures that the core control rod does not insert. times with the rcraininn control rods assuaing the strongest.operabic meet this Specification, will be available to the operator.An allou bic pattern for inoperable contr to be inoper: ble could be many more than the six n11 owed by the SpecificationThe number of rods permittrd late in the eneration cycle; however, the occurrence of more than six could be indicative, particularly of a generic cont rol-rod drive probler and the reactor will be shutdown.
p within the -control rod drive ncchanisn and in particular, cracks in drive internal housings Also if damage cannot be ruled out, then.a generic pcoblem affecting a number of drives cannot be ruled out.
Circumferential cracks. resulting frer s;ress aristed intergranular corrosion have occurred
.in the collet housing-of drives at several Imns. 'lhis type of cracking could occur in a number of drives and if the cracks propagated until severance of the collet housing occurred scram could be prevented in the affected rods.
Limiting the period of operation with a will assure that the reactor will not be operated with a 'large number of rods l
collet housinn.
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B.
Control Rod Withdrawal 1.
Control rod dropout accidents as discussed in the FSAR can lead to significant core damage.
If coupling integrity is maintained, the possibility of a rod dropout accident is eliminated.
l The overtravel position feature provides a positive check as only uncoupled drives may reach this position.
+ hat the rod is following its drive. Neutron' instrumentation response to rod movement provides a verification eg Absence of such response to drive movements after the reactor is critical would indicate an uncoupled condition.
2 The control rod housing support restricts the outward movement of a control rod to less than 3 inches in the extremely remote event of a housing failure, The amount of reactivity which could be added by this small amount of rod withdrawal, which is less than a normal single withdrawal increment, will not contribute to any damage to the primary coolant system.
design basis is given in Section 6.S.1 of the FSAR and the design evaluation is given in The
- To disarm the drive electrically, two amphenol type plug connectors are removed from the drive in and withdrawl solenoids rendering the drive immovabic.
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sert t he drive and is prefe: red since it allows continued cooling water flowThis procedure is equivalent to valving out in the drive.
and minimizes crud accumulation 3.3/4.3-9
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