ML20113H304

From kanterella
Jump to navigation Jump to search
Amend 146 to License DPR-72,changing Upper Limits for Boron Concentration in Bwst from 2,450 to 3,000 Ppm.Lower Limit Remains Unchanged
ML20113H304
Person / Time
Site: Crystal River 
Issue date: 07/23/1992
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20113H307 List:
References
NUDOCS 9207290172
Download: ML20113H304 (7)


Text

_

yw,

  • f6

' h.

UNITED STATES 3

i NUCLEAR REGUI.ATORY COMMISSION WASHINGTON. O C. Mud o

%.~....)

ELQ1LDA_. PAWER CORPQRal[Q1{

(JTY OF ALApiyA CJJ_LQF BylHjiElk CJ1YJ[JA!!{LSE1LLE C1TY OF K.lSSIMMLE CJTY OLLLLSBVRG CJ1LQF HlW_SliYlti&JLACH ANjLylltilliSMMfjljlS100 CLTY OF NEW_.5HyRNA BEA(JJ CITY QF OCALA OllANQQ_VllL11LEL.C.QMM11510N ANQ_(JTY OLQRLAjiQQ illilliO1LILEGIBl0_C.QOPLRAlll(J{C, CITY OF TAl,LAHASS(1 QQLKET__NO, 50-3Q2 CRYSTAL R11ERJfili 3 Hyn[aR.GEBLRAllRG PLAffl 8!ill!DM[ffT TO FACILITY OPERATING LICE!{SE Amendment No. 146 License No. DPR-72 1.

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

A.

The application for amendment by Florida Power Corporation, et al.

(the licensees) dated February 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, 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 (1) that the activities authorized 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; D.

The issuance of this amendment will not be inimical to tSc common 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 Commission's regulations and all applicable requirements have been sat 3fied.

9207290172 920723 POR ADOCK 05000302 P

PDR

. 2.

Accor ngl), 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-72 is hereby amended to read as follows:

Inchnical Specificatt9m The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, are hereby incorporated in the license.

Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the start of the Cycle 9 mid-cycle outage and shall be implemented before startup from the Cycle 9 mid-cycle outage.

FOR TliE NUCLEAR REGULATORY COMMISSION

/7 iJferbart N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuanca: July 23,1992 9

--w, ATTACHMENT T0_LJCENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. OPR-Z2

)

DOCKET NQ2_la:1Q2 Replace the following pages of the Appendix "A" lechnicai 5pecifications with t

the attached pages.

The revised pages are identified by amendment number and i

1 contain vertical lines indicating the area of change.

The corresponding J

overleaf pages are also provided to maintain document completeness.

Re_ move Jnie.r_1 r

3/4 1-16 3/4 1-16 3/4 5-7 3/4 5-7 8 3/4 1-3 8 3/4 1-3 L

B 3/4 5-3 8 3/4 5-3 M

Y r

..,.--.J

Y t!AC ;ViiY CONTt0L $YST PS

$URv!!LLANCE RE*Utt!"ENTS f Continuedi e

3.

Verifying the concentrated beri acid storage system solution temperature when it is the scur:e.of herated

water, b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying f ra SW57 tem:erature when it is the source of cerated water anJ the outside air tem:erature is

  • 40*F.

l CRYSTAL A!ygg. UNIT 3 3/4 1 15 l

l

'N REACTIVITY CONTD0L SYSTEMS BORATED WATER SOURCES OPERATING LIMITING C0!!DIT10N FORJ)PERAT10N 3.1.2.9 Each of the following borated water sources shall be OPERABLE A concentrated boric acid storage system and associated heat tracing a.

with:

1.

A minimum contained borated water volume of 6,000 gallons, 2.

Between 11,600 and 14,000 ppm of boron, and 3.

A minimum solution temperature of 105'f.

b.

The borated water storage tank (BWST) with:

1.

A minimum contained borated water volume of 415,200 gallons, 2.

Between 2,270 and 3,000 ppm of boron, and l

3.

A minimum solution temperature of 40'f.

ePPLL(A_BillTY: MODiS 1, 2, 3, and 4.

eC119d; With the concentrated boric acid storage system inoperable, restore a.

the storage system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 17.

Ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the concentrated boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With the borated water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

CRYSTAL RIVER - UNIT 3 3/4 1-16 Amendment Nos. 8, 15, 20, 32, 46, Et, 77, 36,146

r' TNCY CORE COOLING 3YSTEM_ji C ATED WATER STORAGE TANK

,b j

Y LIMiilNLCONDLI1QN_FJ)R OPBATI0ff 3.5.4 The borated wri<tr storage tank (BWST) shall be OPERABLE with:

)

h.

A contal ied bcer.'.ed water volume r oetween 415,200 and 449,000

gallons, b.

Between 2,P70 and 3,000 pprs of boron, r.nd l

c.

A minimum water temperati,re of 40*F.

A_PPLLCABILITY: MODES 1, 2, 3, and 4.

P ACILO!!:

With the borated water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANOBY within the next 6 liours and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Sjjj]vQLLANCE RE0VIREMENTS 4.5.4 The BWST shall be demonstrated OPERACLE:

a.

At least once per 7 days hy:

1.

Verifying the contained borated water volume in the tank, 2.

Verifying the boron concentration of the water.

b.

At least once per '!4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by verifying the water temperature when outside air temperature is less than 40*F.

CRYSTAL RIVER - UNIT 3 3/4 5 7 Amendment No. 146

The limit established for minimum boron concentration is based upon ensuring that with a minimum BWST level following a LOCA, the reactor will remain subcritical in the cold condition following mixing of the BWST and RCS water volumes. Large break LOCAs assume all control rods remain withdrawn from the core.

The minimum and maximum boron concertration limits both ensure that the solution in the reactor building emergency sump following a LOCA is within a pH range of 7.0 to 11.0 prior to recirculating the solution through the low pressure injection system and the reactor building spray system.

This pH range will minimize the evolution of iodine and minimize the effects of chloride and caustic stress corrosion cracking on the mechanical systems and componcnts within the reactor building.

The maximum boron concentration in the BWST is also based on the potential for boron precipitation in the core during the icng term cooling period following a LOCA.

BWST boron concentrations in excess of the limit could 2sult in precipitation earlier than assumed in the analyses.

Tho OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactisity control while in Mode 6.

3/4.1.3 MOViB1E CONTROLAJSEMBLIES The specification of this section (1) ensure that acceptable power distribution limits are maintained, (?) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effect of a rod ejection accident. OPERABILITY of the control rod position indicators is required to determine control ~ rod positions and thereby ensure compliance with the ;ontrol rod alignment and insertion limits.

(

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ersure that the original i

criteria are met.

For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POWER.

The reactivity worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the safety analysis.

The position of a rod declared inoperable due to misalignment should not be included in computing the average group position for determin n.g the OPERABILITY of rods with lesser misalignments.

CRYSTAL RIVER - UNIT 3 8 3/4 1-3 Amendment Nos. 20, 32, %, 146

4 I

[REaCTIVITYCONTROLSYSTES I

Ba5ES k

3/4.1.3 k

M QLA BL[_QANT R O L A S S EM B LID __LC_o n t i n u til The marimum rod drop time permitted is consistent with the assumed rod drop time used in the sefety analyses.

1

'tasurement with T y 525'F and with reactor coolant pumps opersting ensures at the measured Tr,op, tinc5 will be repre',entative of insertion times experien ed during a reactor trip at operating conditions.

l Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with frequent l verifications r2Qwh ad if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applic bl l LCO's are satisfied.

a e l

OPERABILITY of either rod position indicator (API or RPI) and satisfying I the associated surveillance requirement agreement criteria assures the ability to determine group average position within 1.5%.

The limitation on Axial Power Sha.oing Rod insertion is necessary to ensure that power peaking limits are not exceeded.

i l

4 i

i l

1 l

l i

i lCRYSTALRIVER-UNIT 3 834 14 Amendment Nos.

'!, 25.1'4

The limit established for minimum boron concentration is based upon ensuring that with a minimum BWST level following a LOCA, the reactor will remain subcritical in the cold condition following mixing of the BWST and RCS water volumes. Large break LOCAs assume all control rods remain withdrawn from the core.

The minimum and maximum beron concentration limits both ensure that the solution in the reactor building emergency sump following a LOCA is within a pH range of 7.0 to 11.0 prior to recirculating the solution through the low pressure injection system and the reactor building spray system.

This pH range will minimize the evolution of iodine and minimize the effects of chloride and caustic stress corrosion cracking on the mechanical systems and components within the reactor building.

The maximum voron concentration in the BWST is also based on the potential for boron precipitation in the core during the long term cooling period following a LOCA.

BWST boron concentrations in excess of the limit could result in precipitation earlier than assumed in the analyses.

The 0PERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in Mode 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specification of this section (1) ensure that acceptable power distribution limits are maintained, (2) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effect of a rod ejection accident. OPERABILITY of the control rod position indicators is required to determine control ~ rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.

For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POWER.

The reactivity worth of a misaligned rod is-limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the safety analysis.

The position of a rod declared inoperable due to misalignment should r.ot be included in computing the average group position for determining the OPERABILIT) of rods with lesser misalignments.

l CRYSTAL RIVER UNIT 3 8 3/4 1-3 Amendment Nos. 20, 32, iS, 146 l

~

l REACT;ylTYCONTROLSYSTEMS

- l.

]Ba5ES I

! '3/a.1.3 MQyABLE CONTROL ASSEMBLIES (Continuedl

_The maximum rod drop time permitted is consistent with the assumed rod drop time used in the safety analyses.

Measursment with T 1 525'F and with reactorcoolantpumpsoperatingensuresthatthemeasured8700timeswillbe representative of insertion times experienced during a reactor trip at operating conditions.~

Control rod. positions and OPERABILITY of the rod position indicators are required'to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with fre l verifications required if an automatic monitoring channel is inoperable.quent These vert f tcation frequencies are adequate for assuring that the applicable

-LCO's are satisfied.

OPERABILITY of either rod position indicator (API or RPI) and satisfying the associated surveillance requirement agreement criteria assures the ability to determine _ group average position within 1.5%.

The limitation on Axial Power Shaping Rod insertion is necessary to.

ensure that power peaking limits are not exceeded.

1-

\\

i 1

~l l

l l

l CRYSTAL RIVER UNIT 3 -

B 3'4 1-4 Amendment Nos. , 25,144 o

.e tP.EAGENCY CORE COOLING SYSTEMS b

BASES 80 RATED WATER STORAGE TANK (Continued)

The contained water volume limit includes an allowance for water-not usable because of tank discharge line location or other physical characteristics. The limits on contained water volume and boron concentratior ensure a pH value of between 7.0 and 11.0 of the solution sprayed within the containment after a [

design basis accident.

The pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion crtcking on the mechanical systems and components.

CRYSTAL RIVER - UNIT 3 8 3/4 5-3 Amendment Nos. 14, 146 9

m

-