ML20126K119

Amend 54 to License DPR-16,changing Tech Specs to Incorporate Certain TMI-2 Lessons Learned Category a Requirements Re Emergency Power Supply/Inadequate Core Cooling & Containment Isolation

ML20126K119
Person / Time
Site:	Oyster Creek
Issue date:	03/29/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126K117	List: ML20126K114 ML20126K119 ML20126K122 ML20126K126
References
NUDOCS 8105110502
Download: ML20126K119 (18)

Text

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spantCuq jo,, UNITED STATES g g( g NUCLEAR REGULATORY COMMISSION t rE WASHINGTON, D. C 20555

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JERSEY CENTRAL POWER & LIGHT COMPANY  ;

DOCKET N0. 50-219 ,

OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE i

Amendment No. 54 '

License No. DPR-16

l. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Jersey Central Power & Light l Company (the licensee) dated September 23, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, I' as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; ,

B. The facility will operate in conformity with the application,  ;

the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized i by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities .

will be conducted in compliance with .the Commission's regulations; i L

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of i the public; and {

i E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable l 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 3.B of Provisional Operating License  :

No. DPR-16 is _hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54 , are hereby i 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. i i

FOR THE NUCLEAR REGULATORY COMMISSION t

. l Dennis M. Crutchfield, Ch' f  :

Operating Reactors Branch #5 f Division of Licensing

Attachment:

Changes to the Technical  :

Specifications  ;

Date of Issuance: March 29, 1981 h

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TABLE OF CONTENTS ,

Section 1 Def4nitions 1.1- Operable 1.0-1 1.2 Operating 1.0-1 1.3 Pcwer Operation 1.0-1 1.4 Startup Mode 1.0-1 i

1.5 Run Mode- 1.0-1 1.6 Shutdown Condition 1.0-1 1.7 Cold Shutdown 1.0-1 1.8 Place in Shutdown Condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 1.12 Refueling Outage 1.0-2 1.13 Primary Containment Integrity 1.0-2 1.14 Secondary Containment Integrity 1.0-2 1.15 Deleted 1.0-3 1.16 Rated Flux 1.0-3 1.17 Reactor Themal Power-to-Water ,

1.18 1.0-3 Protective Instrumentation Logic Definitions 1.0-4 1.19 Instrumentation Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4 3

l.21 Core Alteration 1.0-5 t

1.22 Minimum Critical Power Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 i

1.24 Surveillance Requirements 1,0 5 1.25 Fire Suppression Water System 1.0-5  ;

i Section 2 Safety Limits and Limiting Safety System Settings  !

2.1 Safety Limit - Fuel Cladding Integrity 2.1-1 2.2 Safety Limit - Reactor Coolant System Pressure 2.2-1  :

2.3 Limiting Safety System Seetings 2.2-3  :

Section 3 Limiting Conditions for Operation  !

3.1 Protective Instrumentation 3.1-1 3.2 Reactivity Control 3.2-1 3.3 Reactor Coolant 3.3-1 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1 3.6 Radioactive Effluents 3.6-1 3.7 Auxiliary Electtical Power 3.7-1 3.8 Isolation Condenser 3.8-1 ,

3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1  ;

3.11 (Not Used) 3.11-1 3.12 Fire Protection 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1  !

Amendment No. Jt.,7f. 2f, 54  !

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' Page l Section 4 Surveillance Requirements l

l 4.1 Protective Instrumentation 4.1-1 1

4.2 Reactivity Control 4.2-1 l 4.3 Reactor Coolant 4.3-1 4.4 Emergency Cooling 4.4-1 4.5 Containment 4.5-1 4.6 Radioactive Effluents 4.6-1 4.7 Auxiliary Electrical Power 4. 7- 1 4.8 Isolation Condenser 4.8-1 4.9 Refueling 4.9-1 4.10 ECCS Related Core Limits 4.10-1 4.11 Sealed Source Contamination 4.11-1 4.12 Fire Protection 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 Section 5 Design Features 5.1 Site 5.1-1 5.2 Containment 5.2-1 5.3 Auxiliar/ Ecuipment 5.3-1 i'

Section 6 Administrative controls 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications 6-1 6.4 Training 6-2 6.5 Review and Audit 2-5 6.6 Reportable Occurrence Action 6-10 6.7 Safety Limit Vilation 6-10 6.8 Procedures 6-10 6.9 Reporting 2eauirements 6-12 6.10 Record Retention 6-27 6.11 Radiation Protection Procram 6-28 6.12 (Deleted)  !

6.13 High Radiation 4rea 6-28 6.14 Environmental Qualification 6 30*

6.15 Integrity of Systems Outside Containment 6-31 6.16 Iodine Monitoring 6-31 Issued by NRC Order dated 10-24-80. -

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Amendment No. 77, Jf, 54 l I

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J-dcee: w i *"i a9C main *ain an unin?erry *e MOrm a l O l ant shu*Cown Operatien tS~il  !

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2 oces: . itn an; mai nta in an un i nterr uo*ec ncem al :lan? snut:o.n operatien until l ne ::10'snu?::.n_ en.ci*ien is ec . ,

'.:0 3'.a !E l'1 IJCLaTI) 20*10!*10'l .I i

2 : eec . i n an: maintain an uninterructec ncrmal isolation et ?ne reac*er tr:m )

- e ur:!no ::n=enser system incl ucing closure et ? e main steam is01stien 3

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Tne reac*:P is.in *ne refuel moce anen tne reac?ce ecce swi?ch is in the ref uel i

?.cce :csition en: *nere is fuel in ?ne reac*or vessel. In ?nis acce ?ne f ref uel ing cl atterm . inter i:CKs are in : ers-!cn. lt i

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-: Or ?ne pur:cse Of cesignating trecuency et *estiag and surv ei l l ance, a f ref uel ing Outage snel l "'e3n 3 regu l ai' I y scneculec refueiing ou" age; no.ever, i ane-e such cu*3ges Oc:gr .l*91n 3 men?ns Of +5e enc of ?ne =rev ious re f uel i ng f Ou age. ?ne *est or s.;rvei l l ance neec nc? :e perf ormeo until tne nexT reguterly l Fol icwi ng *ne first rotueling Gu?3ge, *ne *ime c e? .een I senacu l ec outaje.

sue:ess Ne tests or surveill unce snci l not exceec ~~, men-ns. f I>

1.1 ;, Oc t vAY *01T A l >1'ENT lit TE 3i:i l *Y .

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r i m e. f :enta i nm ent integri*y means tna? ?ne cr ywell and a:scr: tion enameer see l

se: arc ' al l et ine tel:c.ing conc itiens are satist icc-

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a. AIi mon-su?:m at:0 Orimary : ntoinment ise:ation vsives anicn are nc* f I

ecuirec

• ce :en ter :13n7 ccers?!cn are closec. [

3. A? !ess? cre ::ce in tre sie tecx is closec an: seeiec. I l

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. 2 11 automa?i: co n t a i nm e n * !se!3-ion valves scecifisc in To:le ;.:.2 are  ;

c:ces:? e :r are se: gree in ?ne ciesec 00siti:n.  ;

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AmendmentNo./, , 54 l l

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3.5-la

c. The reac*cr coolant system is maintained at l ess than 212 F anc ventec.

3. At least one core spray pump, anc system conponents necessary to celiver ratec core spray flow to tne reacter vessel, must r em a i n operaD ie to *ne extent that *ne pump and any necessary valves can De  ;

started or operated from the control room or from local control stations, anc the torus is mechanicall y intact. ,

e. (1 ) No work shall be performed on the reacter or it. connected ,

systems which could result in lowering tne reacter nater leve to less th a n d ' 3" acove **e *op of tne ac*ive fuel anc tne concensare storage tank level is greater than thirty (30) fee * ( n0,000 gallons). A? '

leas

• two recundant systems including core saray pumps anc system ccmpenen*s mus* remain ocersole as definec in c. acove. t 5

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(2) ine reacter vessel heac, fuel pool gato, and separator-cryor  ;

pool gates are remcvec anc *he nater level is aceve el ev e*ien 117 ,

fee *. l NOTE: Wnen f i t I i ng tne reactor cav ity f ran the concensa*e t storage *ank and craining tne reactor cavity to the ,

condensate storage tank, *ne 30 fact limit cces no* acply '

Orov idec there is a suf ficient amount o f wa*er to comole*e the ficocing operation.

.t . Primary containment integrity snall be maintained at all times when tne reac*cr is cri*ical or .nen tne reacter water temcerature is above 212

• F and fuel is in the reacter vessel except wnile performing low power pnysics *ests at ,

atmosoneric oressure curing er af ter ref ueling at pow er l ev e l s not to exceec 5 '

1 a) with one or more of the containment i sol at ion valves snc=n in .

Taole ).5.2 incoereele- i l

1. Maintain at ieas* ene isolarien valve operable in each l af+ec*ec Oenetra?ien that is ccen and wi*nin 4 nours (43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> l f or the traversing I n-ccre probe system) el*her; J a) 2es cre ?ne inoperac le vol ve( s) *o coer 3O l e s*atus or i

D) t scl a*e eacn af f ectec senetration Oy use et at leas

• one l Ceac-i v a*ec automa?i c val v e securea in the isolation l cosition, cr i l

c) I sol ate each af f ectec genetraticn by use of a* leas

• cne ,

closec manual v alve or c l i nc f l ange.

2. An incoercD ie conta i nment isolation valve of the snutdown cccling system may se coenec witn a rester nater temcerature ecual to or less than 350 F i n ceder to s t ace *he reac~cr in the Amendment No.,F, fg,54

I 3.5-lb cold snJtdo.n 00ndition. The inocer ab l e val v e s'1311 3e Petarned to the operable $tstus crior to p l acing the reactor in a condition ,here pr imr y :onta l sment in+egrity is required.

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Amendment No. 54 L

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Amendment No. 54

=T-g - v v w --ryr-y-., yyy,p, w.ng , er yy-av y grr7v--gv'"

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i 3.13-1 l l

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3.13 ACCICENT MCNITORING INSTRU W NTATICN j [

l 1 Aeolicsollity: Appiles to the coerating status of accicent f monitoring instrumentation.

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Objective: To assure operability of accident monitoring ,.

I n s* rum entet l on . .

Soecifiestien: A. Relief and Safety Valve Position Indicators

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1. The accident monitoring instrumentation  !

channels snow in Teo l e 3.13.1 shall se operable  !

when the moce switen 15 In the Startup or Run  ;

positions.

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dith the numoer of operable accident '

2.  !

monitoring Instrumentation channel s less than the i

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Totsl Number of Channels shown in Taele 3.13.1, l  ;

eitner restore the inopersble channel s c operable I l

status w i tnin 7 days, or pl ace the reactor in tne  ! i cold snutdown condition withl9 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I f

3. Wits the number of operaole accident  !

monitoring instrumentation channels less inan the i Minimum Channels Opersole requirements of Table i 3,13.1, eitnee restore the insperalt f e emannel( s) to the operable status within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, or place the reactor in the cold shutdown concition wIthin i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j j

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Amendment No. 54

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ine c:oracilit, cf tne accicent menitcring i n s tr um en t at i on ensures ?nat sutticien? intermation is availacie en selectec plant carameters te mon i ter anc access inese v ari a:l es c ur i ng anc f e t icw ing an accident. Inis ecocoility is l censisten? .ith '!t.R E 3 C 5 79 .  ;

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3.13-3 TAlli.li 3.13. I .

s ACCIDI.tfl' PRINI'IOltlNG INSTittlMI NEATinN

'l ul'Al. NO. 01 MINIMilM CllANNiilS I NS'Iltilf t1 NI CilANNiilS Ol*littA111.li

1. Relief and Safety Valve Position Indicator (Primary Detector *) 1/ valve 1/ valve or 1/ valve Relief and Safety Valve Position Indicator (Backup indications **)

Acoustic monitor Thennocouple Amendment No. 54

4.5-4

3. Centinuous- Leak Rate Vonitor

1. When the primary containment is inerted the cun f ainment snell be continuous l y mon i tored for gross leakage by review of the inerting system makeuo requiremen+s.

2. ' This monitoring system may be taken out of service for the purpose of naiatenance or testing b ut s3all be returned to serv ice as soon as practical .

- * . Re:cet cf Test Res,0,f3 Eacn in*egrated leakage rate test shall be tne subject of a summary tecnnical report, including results of tne local leakage ra re tests . The report snel: include analysis and interpretation of the resu l ?S which demonstrate compliance in meeting the speci f ied l eakage rate l im its.

I. runctional Test of Valves  ;

1. All containmant i sol ation v alves specified in Taole 3.5.2 shall se tested for automatic closure by an isolselon signal during eac, ref uel ing otuage. The following valves are required to close in '9e time soeci f ied below:

Main steam line isolation valves 2 3 sec. and $10 sec , l isolation condenser isolation valves 660 sec. j Oieanuo sys*+1 isola? Ion valves 400 s ec . '

",leanup auxil iary pumps system isolation val ies 660 sac.

Shutdown ,y stem i sol ati on e sives 56^> sec.

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2. Each containment isolation valve shown in Table 3.5.2 shal.1 l De demonstrated operable prior to returning the valve to service af ter maintenance, repair or replacement work is perfor.ned on the

/ 31/a ar **t tsia: '.t r+1 oc tua tor a f :/cl ing ho / al /a Phro;gh at

3ast one comp l e'e ycle of full travel and verifyI ig tne specifled i sol ating time. Fol lon ing m ain*enance, recale or replacement .cek en ee control or power circu i t for the valves 3,own 11 ~ c3 l e 3. i . 2, ".o st?+: +1 coop 3nant s% sit %s res ed to n 3c e it nill perform its intenced function ln tne circuit.

3. During seriods of sustained power operati:n eser main steamline isolation valve shtil l :e exercised in accorcance with

• ne foi Tow i ng schedu le.

s. Dall y tests - Exerci se salve (one at a time) to approximately 95% open position wl n reac*or at operaticn acwer level.

b. Quarterly tests - Trio valve (one at a time) anc 09eck full closure time, ni*n reactor power nar red rar Pqsa $ 3 7, M ?.3 ed p3.or.

Change #

Amendment No. 54

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4.13 AC010ENT MONITORING INSTRUMENTAT! N, 1 i i AcoI,I:a0lIity: App!les to surveliIance requirements for the j accident nont toring instrumentation. .t Objective: To verify the operability of the accident i monitoring Instrumentation. j Soecificatien: .A.- Relief and Safety Valve' Position Indicators'

1. is::S 4ccideor nioni toring ins tronenration thennel shalI be demonstrated operable by perf ormanca of 'the Oh.3nnel Oheck  !

and Channel Oalibration operations ,  !

at the trocuencies shown in i Taole 4.13.1. l l

Bases:  ;

l tSe opersbiliP/ of *he accident nonl*oring instrumentation ensures l

' *hst suf ficien t information is aval l ao le on sel ected ' pi ant para.neters i to monitor anc' assess these /ariables during and following an I l sc:i. d ent . This escabi!ity is consistent nith NUREG 0579. j i

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Amendment No. 54

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TAlitti 4.13-1 AO:lDI.Nr HONil'Ol(ItJt; INSTININiiffrATION SIlitVlill.l.AN(:li itigilltl Hi t(IN GIANNI:1. GIANNiii.

.I NSTRilMINI' G11EE I:A1.1IIHATION

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1. Relief and Safety Valve Position Indicator A g (Primary Detector *) A n -

Relief and Safety Valve Position Indicator (Backup Indications **)

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$ 1.egenil:

g ca.

i e g Au at least tmee per .51 ilays ; 11 = at least once per 18 mimtlis (559 stays),

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O g Acoustic Monitor Y-in m D **

Thermocouple i .

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I ADMINSTRATIVE CONTROLS i

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'6.1 RESPONSIBillTY I

6.1.1  ;

The, Director, Oyster Creek Operations shall be responsible for overall facility operation and'shall delegate i n writing the I succession to this responsibility during his absence.  !

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i 6.2 ORGAH 12AT 10f 4  ;

i 0FFSITE 6.2.1  ;

The ottsite organization for technical support shall be as shown on j Figure 6.2.1.

1 FACILITY STAFF t

t 6.2.2 The facility organi:ation shafI be as shown on Figure 6.2 2 and:

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a. Eacn on duty shift shall include at least the shift staffing Ind icated on Figure 6.2.2. j t

b. At least one licensed operator shall be in the control room when l tuel is in the recctors ,

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c. Two l icensed operators shall be in the control room during all l reac4r startups, shutdowns, and other periods involving planned f control rod manipulations. l

d. ALL CORE ALTERATIONS shalI be directiy supervised by eIther a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Hanaling wne has no other concurrent responsibil ities dur ing i this operation. {

e. An individual cualified in radiation protection measures shal l l De on site enen fuel is in the reactor. {

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t. A Fire Brigade of at least 5 members shall be maintained onsite  ;

at all time. The Fire Brigade shall not include the minimum shift j crew necessary for safe shutdown of the unit or any personnel i required for other essential f unctions during a fire emergency. f

g. Each on duty shift shall include a Shift Technical Advisor except l that the Shift Technical Advisors position need not be filled if l the reactor is in the refuel or shutdown mode and the reactor l is less than 2120F. j 1

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i 6-1 e Amendment No..J5' M , M I54

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I plant. A maximum of four years of this five year experience may be i ful filled by related technical or acacemic training. I Shit

• Tecnnical Advisce  ;

2 .

1' R e c u i rem e n ts : S ache l cr's degree or _ eculvalent in a scientific or  ;

engineering discipline with specific

• raining in plant design, and resocnse and l analysis of the plant for transients and accicents. ,

s i 5.3.2 ,

Each member of the raciation protection organization for which there }

is a comparable position described in ANSI N16.1-1971 shall meet or l exceed the minimum qualifications scecified *nerein, or in *he case 1 of. rad _lation' protection technicians, they shall nave 'at least one year's continuous experience in applied raciation protection work in a nucleaar f acii ity deal ing

• i*n reclological. scoblems similer to

? nose encounterec in nucl ear power stations, and snali have been certified by the Radiolog ical Controls Manager, as qualified to  ;

perterm assigned functions. This certi f ication must . be based on an i NRC approved, dccumented program c0nsisting of classrocm training -

witn appropriate examinations anc documentec positive f incings by s responsible superv i s ion that the I nd iv idual has demonstrated his  !'

eDility to perform each specif ied precedure and assigned function with an uncerstancing of its basis and purpose.

5.4 AAINING  !

i $.4.1

'l A retraining pecgram for operatcrs shal I be maintained uncer tne direction of the Manager, Training and snall meet tne requirements ,

anc recommendation of Appencix A of 10CFR Part 55. Replacement training programs, the content of whicn shall meet the recuirements  ;

of 10CFR Part 55, snall be conducted under the direction of the  !

Manager, Training for i Icensed operators and Senior Reactor j Ocerators. l l

l 5.4.0 i A training program for t9e Fire Brigace shal I be main *ained uncer tae direc*lon of the Vanager, Training. j 5.5 St.:ITY REVIEW AND AUOli i t

The Directer Cyster Creen Operations and three organi:stional uni *s, j the Plant Co; ations Review Commit *ee (PCRC), the incependen* Safety Review Groups ( l SRG ) and the General C f f ice Rev iew Boarc (GCRS) func*len +o acccmplisn nuclear safety review and aucit Of the Oys*er 3 Creen Station. '

6-Ob Amendment No. A T, g 54 e - - , . - . . - , - - . , . -. ., -.~s y .n --w . , - - , . . , - - ,,

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I 5.5.1 Direct:r :<srer Creek Oeersti:ns (2000)

.: UNCTION 6.5.1.1 The Director Oyster Creex C erstions snelI ensure that:

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I 6-:: Amendment No. 54

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6.15 Integrity of Systems outside containerant ,

The licensee shall implement a program to reduce leakage from systems outside containment that would or. j could contain highly radioactive fluids during a  ;

serious transient or accident to as low as practical i levels. ~This progra= shall include the followingt i

1) P,9 visions establishing preventive maintenance and periodic visual inspection requirements, and  :

2) System leak test requirements, to the extent permitted by system design and radiological  !

conditions, for each system at a frequency,not to exceed refueling cycle intervsls. The systems  !

subject to this testing are (1) Core Spray, t l (2) Containment Spray, (3) Reactor Water -

Cleanup, (4) Isolation Condenser and (5)  :

Shutdown Cooling. l f

l 3

6.16 Iodine Monit o rin:1 [

The licensee shall implement a program which will ,

ensure the capability t o a ccu ra r e ly de t a rmitie the i airborne iodine concentration in vital aress* under  ;

accident conditions. This progism shall include the j following:

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1. Training of personnel, 2, Procedures for monitoring, and '

3. Provisions for maintenance of sampling and analysis equipment.

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• Areas requiring personnel access f o r es t ablishin-g hot shutdown condition.

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6-31 Amendment No. 54 l 1

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