ML19317G785
| ML19317G785 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/17/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G765 | List: |
| References | |
| NUDOCS 8004010611 | |
| Download: ML19317G785 (9) | |
Text
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b UNITED STATES e
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NUCLEAR REGULATORY COMMISSION g
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s.,.....f SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.17 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Sacramento Municipal Utility District (the licensee) dated November 10, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.l/, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l$ u f
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Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: December 17, 1977
s ATTACHMENT TO LICENSE AMENLMENT NO. 17 FACILITY OPERATING LICENSE NO. DPR-54
-DOCKET NO. 50-312 Revise Appendi> A'as follows:
Remove Pages Insert Pages 1-5 & 1-Sa I-5 1-6 6-12 6 6-12d New pages and changes on the revised pages tre shown by marginal lines.
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RANCHO SECO UtilT 1 TECH!llCAL SPECIFICATIONS DEFINITIONS D.
All automatic containment isolatiori valves arc operabic or closed In the safety features position.
E.
The contal rrnent leakage satisfics Specification 4.4.1 and no known changes have occurred.
l.8 Rr.rORTABLE CCCtl::f.U:CC Defined under Administ ative Controls Section 6.9.4.
l.9 TiliE PEnl0DS, 15,1 Shift A time period covering eight (8) hours, three shifts equally dividing a twenty-four hour tinae period.
l.9.2 Daily A tirne period within o twenty four hour spen from 0000 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> fron, Monday through Sunday.
193 Veel.l y A tinie period f ro i Monday through Sunday spaced to occur fifty-teo thnes a year.
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1.9.4 M,nthly A t irne perihd f rom the first to Icst day of
/, talendar noreth spaced to occur tucive tiraes a year.
195 Quarterly A t irie period of three calendar rnonths spaced to occur four tiraes a year.
1 9.6 S en.1 - Ar.nua l l y A tic:a period f rom January I and July I covering the subsequent six months.
1.9.7 Dicnnually_
A t ire.e period of twenty-four calendar rnonths spaced to occur once in tua years.
1.10 SAFETY Safety cs used in t!.c se Technical Specifications shall raean nuclear saf t.ty and shall cnte: pass all sycic cs cnd components that hcve or raay h:.ve en e f fec t c.n the health and safety of the general publ.c.
'HIIS DOCUMENT CONTAINS POOR QUALITY PAGES gg Amendment No. 17
o admit!!S1RA1 IVC COMTECL5 h.
The change is approved by two members of the. plant management staff, at Icast one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The chcoge is documented, reviewed by the PRC and approved by the Plant Superintendent within seven (7) days of implementation.
6.9 REFORT I NG RF.0t!! P f ttE NT S 6.9.1 In addition to the applicable report ing requirements of Ti tle 10, Code of federal I;c9ulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unter,s otherwise nc.ted.
51/iRTilp RET'OR1 6.9 1.1 A summary report of plant startup end power escalation testing shall be submitted following (1) Receipt of an operating license: (2) anendnent to the licer.se involving a planned increase in power level; (3) instal-lation of fuel that has a different design or has been manufactured by a dif ferent fuel supplier; and (4) rc.odifications that may have signifi-cantly altered the nuclear, thermal or hydraulic performance of the plant.
The report shall address each of the tests identified in tie TSAR, and,shall include a description of thc ixasured values of the operating conditions or characteristics obtain d d" ring the test psogram and a comparison of these values witn design predictions and specificatloas.
Any corrective nr.tlons th t ucre required to obtain 9
satisfcctory operation shall also be described.
Any additional specific deintls required in license conditions based on oil.cr comit-ments shall be in:lud:d in this report.
6.9 1.2 Startup reports shall be submit ted within (1) Minety (90) days following completion of the startup test program; (2) !?inety (90) days following resumption or commence:.:ent of commercial po..er operation; or (3) lline (9) m:,nths follo.ing initial criticality, whichever is earliest.
If the Startup neport does not cover all three events (i.e., initial criticality, complet ion of startup tet.t progran end resu. pt ion or co:..cncement of con.nerical re.:cr operation), supplerentory reporis shall be su!mitted at least every three (3) icont hs until all three events have been co*.:pleted.
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6-12 Amendment No. 17
EllVI P.M_'tE!!TAL REPO3T (i.9. 2 The Envi ronrnent al 1(e,> ort required within Appendiar D shall include a tabult. tion on an annual basir. of the nunScr of station, utility and other personni.I (including contractors) rocciving exposures gre. iter than 109 rirce/yr an 1 the'r assoc lated ran rem exposure t.ccurding t o wori, and job f unc t ions.*, e.g., reacter ope rc;t io:is and su rvc i l l ant.e. i tr..c r v i c e i s.;;.ec t ion, routine r.aintenance, special r.1a i n t enanc e (d.. s c. r i !.e s.'aint enent e), wast e process ir ; and ref ucling.
The rio:.n ass i c,n..:nt 't o ve:r io.: du t y f unct ions r.ay be es t irnc t e s based on pocket des ii.ct er, T L D, or f i lr.. badge r.ea surcinen t s.
Srna l l exposures totalin;, less than W. of the individual totc.) dose need not ha accounted for.
I n t he in g g r e.:a t e, a t least 20? cf the totcl whole body dose rccci'eed fro. cxternal sourccs shall be assigned to speci fic r.ajor work funct iom.
M01:THLY Cif'OP.T 6.9.3 Routine reports of operct ing ttatistics, includine narrative sur.tary of o;>crr.t i ng and r.hu t dr.:n exp.u i ence, of r.t.j or sa fct y rclat ed tr.o i rit taance,
and tabulat ions of f,icil i t y che.c..et, t est', or experir.icr.ts requi red pursur.nt to 10 CFR 50.59(b), shcIl be sobaitted on e nonthly basis to tha Office of "anagement Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, with a copy to the Regional Office, postmarked no later than the fifteenth day ot each month following the calendar month covered by the report.
REPORTAi!E OCEt W f PES 6.9,4 The RE PTRT/,'.L E Oc t C.',' :.". E r. of S;u i f i cat ier.s (. 9.4.1 at d 6.9. 4. 2 be l ow, including correctiv: c e t i er.- cr d neatorer to prev.:nt recur rer.cc, shcIl be repu: t ed to the IP.C.
S ur r i c e.cn ti l rcpt. cts rcay be requirca to fully det.cribe f inal resol.it ic n c.i oc c ur rvnce.
In case of ccriccted or surplc n u. : report:, e licen.s e evtot r e;.o r t :,hn11 be coupletec: c r.d refct em. si.r.11 1,; s..
te t he c.f i.inal repui t date.
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- This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
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AmendmeTt Noo 17
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PROMPT NOTiflCATION VITH WPlTTfN FOLLOVUP 6.9.4.1 The types of events listed below shall be reported within twenty-four (24) hours by telephone and confirmrd by telegraph, mailgram or facsimile transmission to the Director of the Regional Of fice, or his desigt. ate, no later than the first working day folloaing the event, with a writ ten folloaup report within two weeks. The written follouup report shall include, as a minimum, a completed copy of a licensee event r e po r.t forn.
Infor.tation provided on the licensee event report form shall be supplemented, as needed, by additional narrative roterial to provide conplete explanation of the circurastances surrounding the event.
a.
Failure of the reactor protection system or other syste.ms subj er.t to II.r.i t ing sa f ety syst e.m set t ings, to ini t iate the required protective function by thc. time a monitored parc-neter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or failure to complete the required protective function, b
Operation of the unit or of fceted systems when any par encter or operat ion subject to a limiting condition for operation is less conservctive thsn the least conservative aspect of the liraiting condition for cperatica established in the technical sp2cifica-tions.
c.
Abnorr.al degradation discover ed in fuct cladding, reactor coolant pressurc boundary, or primary.containr.cnt.
d.
Pcact ivity enomalle; involving disagrecmant with the prc.dicted value of reactivity balance under steady state conditions during po.er operation greater than or equal to 15 AL/k; a calcule t ed react ivi t y balance indicat ing a Sll'JTDOW lt'J'.G IN less conserv.'tive than specified in the Technical Specifica-tions; short-term reactivity increases thet correspond to o reactor period of ler.s than five (5) seconds or, i f sub-critical, an uhplanned re:ctivity insertion of r.: ore th'n 0.5% AL/h; or o:eurrence of any unplanned criticality.
Failure oc iN.l funct ion of one or r ore cor:pc.nent s which pi event s c.
or could pr event, by i tsel f. the fulIi1Ir.cnt of t he f unct ior.al requirs.:ents of system (s) used to (. ore wit h accidents analy.ud in the St.R.
f.
Personnel error or procedural inadequacy which pr events or covic prevent, by i tsel f, the ful f il lr.ent of tha fun:tlor.a! requirc-cent!. of system.s required to copa wit h eccidents. cnaly: cd in the SAR.
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PF.0lWT ::OitiICAT 10:1 t!!1H t?P.lTTEf: F01 L 0klUP (cont inued) 6,9.4.1 g.
Condit ions arising f rom natural or man-rnado events that, as a direct ret. ult of the event, require plant shutdoan, operation of safety syt.tems, or other prutective encasures required by technical specifications.
h.
Errors dit.co.cied in the transient or 6ccidant analyses er in il.c rict hods usmf for such analyses n described in the Safety Analysis f.ennet or in the bases for the lechnical Specifications that have or (quid have permit ted reactor operat ic,n in a r:ariner ICss conser vat ive than assut..cd in the analyscs.
i.
Pe r f orr.anct. of structures, systems, or corponent'. that requires rcracc'iul Cction or correct ive r aasures to prevcot operation in a raanner less conservative thcn assu.:cd in the accident enalyses in the Safet y Analysis Pepnrt or Technical Sp:cificaticns be.ses; or discevery during plant life of ccr.ditior.t, riot specifically considered in the Safety Analysis P.a; ort or Technical Specifica-tions that regnire re:.:edial act ion or corrces ive reccsures to pr even t the c>.istence or development of an unsafe condition.
THI RTY DAY tii ITT E!!..RE P0f:TS-6.9.h.2 The typeu of eventr. Il<ted belo.4 sloll he the sub,ir.ct of uritten reports to the Dir ector of tiie hegic.nal Of fice within t hirty (30) days of occurrenc.e of the event.
The written report shall include, as a mi n ir.un:., as.pleted copy of a liceneec event report foro.
Infornetion provided on the licensee event-repart forrr. sha l l bc.
supple:.ented, as ncxded, by addi t ional narrat ive noterial to provide co:rplet e er.planat ion of the c.ircut.ist ances 5.urrounding the evc nt.
a.
Reactor prot ect ica syst e.i or engineered scfety f eat ure inst r e-nent settings which arc found to be less conservative thr.n those established by the lechnical Specifications but which do not prevent th': folfilln:ent of the functional requircrcents of af f ec t ed systy. >.
h.
Conditiont I c.W i n,r, t o opera t i on i n a deg raded rc.oh p e rrc i t i c d by a 1imi t ini; cc::di t 100 for 0;. ara; ion or plant shJldy..ra required by a lir.:it.in;i conJit ion for operct ion.
C.
05sctved itied;quacies in the ii pl cnen t a t i on cif acl. iin i s t rat i ve or pro cdural cc.ntrels which thrcaten to cause reduction of c
degree of red.:ndar.c) prrvid. d i n reac tor proi cc iion syst ew.
or enr,ineered sufcty icate:e systc r..
d Abnor:. al c egra/n! ion of sy51ccc.s ot he. thcn ihose specified
-e.
in 6.9.!.I.c shtve das igru,'. t e c or.t a ln rod i oac t i ve ra t er ia l i
resulting fre~ the fissioi. precess.
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$PTCI AL 1:Ir0r.15 6.9.5
'special reports.shall be submitted to the Director of the Regulatory Operatiores 1:tgional Office within the time period specified for cach repo rt.
1hese reports shall be subuitted covering the activities identified Lelow pursuant to the requirement,s of the applicable reference specification:
A.
A one-t itie only, "t:arrat ive Su.: nary of Operat ing Experience" will be, r.u!>mittpd to cover 'she transit ion period (calendar year.1977).
D.
A Reactor Guilding structural integrity report shall be submitted within ninety (90) days of completion of cach' of the following tcsts covered by Technical Specification 4.4.2 (the. integrated leak rate test is covered in Technical Specification 4.4.1.1).
.1 Annual inspection
.2 Tendon Strest Stirveillance 3
End Anchorage Concrctc Survellianec:
.4 Liner I' lote Surveillance C.
Inservice insp.clio.i Program.
D.
Iteserved for; Proposed' Amendment !!o. 43.
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6-12d Amendment No.
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