Text

Amends 78 & 71 to Licenses DPR-42 & DPR-60,respectively, Revising Tech Specs to Place Addl Requirements in Sections 3.15 & 4.1 Re Core Cooling Sys
	ML20210C106
Person / Time
Site:	Prairie Island
Issue date:	08/28/1986
From:	Diianni D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20210C083	List: ML20210C106;
References
	NUDOCS 8609180244
	Download: ML20210C106 (11)
	v • d • e

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f* "%9[h, UNITED STATES y_

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NUCLEAR REGULATORY COMMISSION 5 l WASmNGTON, D. C. 20555 s 1,

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NOFThERh STATES POWER COMPA!W DOCKET NO. 50-282 FRAIRIE ISLAND NUCLEAR GENERATIhG PLANT Uhli h0. 1 AMENDMENT TC FACILITY OPEkATING LICENSE

cendnent I4c. 78 License No. CPE-42 1.

The Nuclear Regulatory Commission (the Cummission) has found that:

A.

The application for emendment by-Ncrthern States Fcwer Company (tLi.

licensee) dated June 6,1986 complies, with the standards er:s require-n er,ts of the Atcr,ic Energy Act of 1954, as amended (the Act), tod the Cornissict.'s rules and regulations set forth in 10 CFR Chapter I; B.

The facility will ograte in conforaity wit.% the application, the provisions of the Act, and the rules and regulatiors of the Ccmission; C.

There is reasonable assurance (1) that the activities authorizec by this amendment can be conducted without endan'gering the health and safety of the public, and (ii) that such activities will be conducted in coirpliance with the Commission's regul6tions; D.

The issuance of this amendrent will nct be inimical to the cornon defense und seChiity or to the hedlth and Safety Of th6 public; and E.

Ti.e issuance of this arnendment is in accordance with 10 CFR Part 51 of the Comn1ssion's regulations ar.d all applicable requirec.ents have been settsfied.

8609180244 860911 PDR ADOCK 050002E2 P

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Accordir. gly..the licenses are' amended by changes to the Technical

~

Specifications as indicated in the attachment to this licer.se amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-42 are hereby amended to read as follows:

(2)~ T,echnical Specifications

.The Technical Specifi. cations contained in Appendix A, as revised througn Amendment _No. 78, are hereby incorporated in the license. The licer'see shall operate the. facility in accordance with the Technical Specifications.

3.

This licer.se amendment is effective as of the date of its issuance.

FOR THE h0 CLEAR REC-l'LATORY COMMISSION k,*

k.

, 4. p%% s ft. wv. a c L Dominic C. Dilanni, Project Manager Project Directorate el Civision of PWR Licensing-A-

Attachment:

Changes to the Technical Specifications

Cate of Issuance: August 28, 1986.

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UNITED STATES

[ ',, *.;.,- ( i NUCLFAR REGULATORY COMM1SSION E

V.EHING TON. D. C. 205S5 "g\\' ' Ih[f f

c,

....+

f!ChlRERN ETATE5 POWER CCMANY DOCKET 60. 50-306 PR9:F IF ISLAhD NUCLEAR GEf4EFJTING FL ANT _ UNIT N0. 2 APEM. MENT TC F ACILITY OPFFAilf4G LICENSE Amer.dr.ent Sc. 71 License No. DPF-th 1.

h Nuclear Pcsuictory Comission (tr,e Commissictd has found that:

i A.

The applic6tior, for ameqdr er,t by Nartbern States Power Company (it.t licer.see) dated Jur.e 6, 19Et complies with the ster.dards and require.-

ments of the Atomic Ei.ergy Act of 1954, cs emseced (the Act), cnc the Corr.ission's rules and rerelations set forth in IC CR Chapter 1-B.

The f acility will operate in ccnf orn,it3 with the applicatier.,

the provisions of the Act, and the rules 6nc reculations of the Camissicn; C.

There is reasciuble issurance (1) that the cctivities authorizec by thi:, emendment can be concucted without endangr:rir:9 the healtt y

and sLfety of the public, and (ii) that suct. activities will be conducted it. compliar.ce with the Comr.ission's regt'lations, E.

The issuer.ce of this unendment wili not be inirdcol to the cctran defense and security or to the health and sdfety af the public; ond L.

The isstence of this Enenament is ir accorder ce witi' 10 CFF Part 51 of the Comission's reguletiure and all applicabic requirerrern have been satisficc'.

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t w 2.

Accordingly, the licenses are amended by changes to the Technical Specifications as indicated in the attachmert to this license er,endment, ar.d paragraph 2.C.(2) of Facility Operating License

.No. CPR-60 cre hereby apenced to read as follows:

(F), Technical Specifications The Technical Specifications containeo in Appendix A, as revised through Amendment No. 71, are hereby incorporated in the license.

The licensee shall.

operate the facility in accordance with the Technical Specifications.

3.

This literse amendcent is effective as of the date of its issuance.

FOR ThE NUCLEAP REGULATORY COMMISSION

.i k

[]: w.A, As. ( /., <, &.,. ~ x rominic C. Dilanni,' Project Manager Froject Directcrate el Division of PWR Licensing-A

Attachment:

Changes to the Technical Sp(cificaticnc Date of Issuance:

August 28, 19E6.

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ATTACPMENT TO LICEtiSE AMEN 0 MENT NOS. 78 AND 71 TO FACILITY OPERATING LICEhSE NOS. DPR-42 AND DPR-60 DOCKET h05. 50-282 AND 50-306 Pepisce the following pages of the Appendfx A Technical Specifications with the' enclosed pages as indicated.

The revised pa5es are identified by anendment nunber and contain vertical lines indicating the area of changes.

Remu*'t Insert TS-fil

.5-iii TS.3.15-1 TS.3.15-1 TS.3.15-2 T5.3.15-2 Table TS.3.15-1 Table TS,3.15-1 Toble TS.3.15-3 Table TS.4.1-1 (Page 4 of 5) Teble TS.4.1-1-(Pege 4 of 5)

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TS-11f l '.3 RM

[W 7ABLE 0F COM ENTS

)

TS SECTION TITLE PMM t

3.5 Instruments. ties Sysn e TL 3.1 t l

3.6.

Containtent Syrre:

IS.S.6-;

A. Ccntainment Systro Integrity 70.3.6-1

,B.' Containnent Joterso! Possure 75.3. M C. Containment end Sh!41d batiding Air Tenper.sturs:

75. 3 A-3 D. Containneet W il letperature Y5.3,6-3 E. Emergency Air Treat'3n'!t Syvtecs TS. 3. 6-3 fs F. Electric Hydregen Escer;biners TJ. E 6.'31 i

3,. 7 Auxiliary Electifca1 Systecs 4.12-1 3.6 Refueling and Fue) Cand Ung

. 7C. L E- )

D. Spent Fuel Fool Specia.1 Pe.ntiJetionJ57. stet 16.1. 6 3 3.9 Radicactivr Ef fluer.ts' E..) 9-:

A. Liquid Effluent's W 3.M B. Geseous Efflucnts M, $, %5 C. Solid'Radioattive VM te M. ), *t j

D. Dose from A11 L'rsnier fuef Cyci. : Secr ets 7F. 3.,9 7 E. Fadfoactive Ll w id Ef G oent V.cnh o:ing

?J ' L%7 3,

Instrumentative

-F. ; Radioactive CarstW Efiluanc ("ct. Ate #:;cr h,3. 4-9 L

'instrumentatic:

l 3.10 Control Red and hwt RXhrthun LNti ff J.1r-t A. Shutdown hactlytt;.

M.3..U+i B. Power Distribt.t Vt; 1,initt 13,.3,141 C. Quadrant Pover h it Lleits MO<!bi

. T). Rod Insertion Li%cs.

TE.'s.] N

E. Rod MisaliprJena 11datiem ib S.10-5 i

T. Inoperable km,t NtiU.on It!$.:6n '.N.thtoy

! L 3..! N G. Inoperable Rod J.!c..'A g?.x2

75. J 1 M t

E. Red Drop Tir.e N.3 W

1. Monitor InopenH11*.:.y behnte ;

% 3.1 >- 7

. L 3.;0-f i

J. DNE Parametera 3.I1 Core Surveillonce Icecnr.?-t tw:1cm k 4.? M-;

'3.12 Enebbers

'f^ 5. D I 3.13 Centrcl Roon Air Treat.nnt inj ac F.3d H 3.14 Fire Itet ection and Ernect Ac'. Jydept A. 3. R-1 A. Fire Detectiov. I.ngtran gtsc %n

.% e. '. ? d B. Tire SuppressAot Wt3r Trye*.c TS. 2. N -I C. Spray and Spricklee $yster4 75.3.js-2 D. Ca;-bon Dioxide Syster W 1 14-3 E. Fire Hose Sections SS. Me-3 F. Yard Ey.drant Hose bovses TS a.Wa G. Penetration nre Barri6tr 76.3.16 6 3.15 Event k nitoring 'Estrumentstcivo 7h 3. ISA A. Precen Moratot s T.L l.!$-2 B. Radiation Monitois 70 9.15-i C. Teactor Wssel 1.* vel Instrueenutism M %1N

]

watet w w %.m.u.7e Unit W. 2s 14 w e n - W. ti. /J. 71

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N, TS.3.15-t

'](1 REV 15 P

7. I1 In.57 tM.1TCRNG INSTRCEIATZO::

JpJ icd 3jlig l

. Applies to rient instrumentatics which does not perfere a protective T

furetion. but shich provides information tc monitor and assess 1 portant parasiters deting and follcuicy; sm acc ident, l.

Q1ectty i'

].

IN ensuY e that suffitirat inf>rsatier. is ava,ilable 'to operaters to deter,uics the aff ecte of and estermine ti e course cf an accident to the extent required to.e'arry c,i required renuaj actions.

3

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fpeciticetter

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6. freecso X5dtm

),

L The evett cenite.rirs instructeret. ion channels specified in Tehle T3,2.15-1 pusil be OperabJe.

2, W3th the netter of Dreeable evene. monitoring instrucentaticn

.thannels less th nn the Ecquired Total Kurber of Channels shewn i

[

cn 74hle T5.3.33--1:..eith.ev restore the inoperable channels to Gpeystle stetus withit seven days, or be in at least Hot Shut-i I

devn withio ubv cext 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

). With the rattrr af Operabic event monitoring instrumentation thanne1r leri chin the Minteur Channels Operable requirements

~

of Tatie 75,3,3 5+.5, either restore the etnicum number of channels tc 6ptreble a:atus within LS hour = or be in at least Hot Shutdevn vithin ghe next 12 hcurs.

Es fgQ1211cn>VnLters l

S. The reest.ronitoring instru entation channels specified in Tati: T5,3.lb-2.shell be Operable.

l

2. With the nuaber of Operable event conitoring instrumentation channels lets than the Pequired Total Number of Channels shown en Table 1$.3,15-2, sither restore the inoperable channels to Operable sta us vithin seven days, or prepare and submit n special report to the Concission within 30 days outlining the i

act. ion talent the Sause cf the inoperability, the plans and the c

schedule. for restoring the system to Operatie status.

I

3. G1th the number of Operable event monitoring instrueentation channels less than the Minimum Channels Operabic requirement of Table TS.3.15-2, initiate the preplanned alternate method of zonitorint the apptepriate parameters in addition to submitting the report required in (2) above.

Unit No.1 - Arrendment No. /4E, //:, A3 Unit ho. 2 - Amendment Nc. /40. E7, ff

TS.3.15-2 KEY C.

Specification - Reactor Vessel Level Instrumentation f

i

1. The reactor vessel level instrerentaticin channels specified in Iable 75.3.15-3 shall be operable i

2. With the number of Operable reacter vessel level instrumentation

}'

. channels less than the Required Total Eurber of Channels shovi en Table TS.3.15-3, either restore the inoperable channels to Operable status within fourteen days, er be in at least Hot Shutdern withir.

the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I

3. With the number of Optrable reactor vessel level instrutentatien channels less than the Minieur Channels Operable requirements cf Table TF.3.15-3, either restere the einicut number of channels te l

Operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months er be in at least Hot Shutdcen withir i

the next 12 hcurs.

l Easis sufficient The operability of the event nonitoring instrumentation ensures that information is available on selected plant parameters to conitor and assess these variables during and following an accident. This capability is censistent with the recom=endations of.*;UREG-0578, "!M1-2 Lessons Learned Task Force Status Report and Short Ter Reconcendations."

Core exit thereoccuple readings necessary to meet the requirements of Specifica-tien 3.15.A are available from the Plant Process Computer, the Control Rect Core Exit Thermocouple Display or if r.o other readout is available, from test equip-readings from the Ccre Exit Thercoccuple Junction Boxes.

r_ent Unit No. 1 - Amendment i,0. Af, f 2.7; Unit No. 2 - Amendment No. 4., 57.7 1

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TARIE'TS.4.1-1 (Page 4 of-5)

MINIMUM FREQUENCIES FOR CllECKS, CAI.IBRATIONS AND TEST OF INSTRUMENT CilAt'NEl.S Channe)

Functional

Response

Description Check Calibrate Test Test Remarks 2(> d. Reactor Trip Bypass NA NA M(1)

R(2)

1) Manually. trip the undervoltage trip attachment remotely (i.e. from the Breaker protertion syntem racks).

2) Automatically trip the undervoltage trip attachment 27.

Turbine overspeed NA R

M NA Protection Trip Channel 2"d. Deleted 29.

Deleted 30.

Deleted 31.

Seismic Monitors F

R NA NA 1

32.

Coolant Flow - RTD 5

R H

NA Bypass Flowmeter 33.

CRDM Cooling Shroud S

NA' R

NA FSAR page 322-56 g g 34.

Reactor Gap Exhaust Air S

NA R

NA yg Temperature y

g" 35a. Post-Accident Monitoring M

R NA NA locludes all those in Table TS.3.15-l lustruments (except for containment' hydrogen

- =

smonitors which are separately to -

specified in this' table)

k. s

h. Post--Accident Moni toring D

R M.

NA Includes all those in. Table TS.3.15-2 g

gg Radiation Instruments mme

, ya

c. Post-Accident Monitoring M

R NA NA

' Includes alI those in Table qg g

TS.3.15-1 ee r*

r+

Reactor Vessel Ievel s-H gg Instrunentation O

kh 36 Steam Exclusion Actuation W

Y

?1 NA See rSAR Appendix T, Section 1.14.r.

,s-u-

, g' System

.~

u ss

! A R

R NA i n st rismen t Chanceln for PORV Control

,5) 17.

Overpressure 111t igat ion lorindine Overpressure Pfi t ig.* t i on y

System m

m Svst ern i

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.-

ML20210C106

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