Text

Proposed Tech Specs Re Moderator Temp Coefficient,Reactivity Control Sys,Rod Program & Axial Power Shaping Rod Insertion Limits
	ML20246P724
Person / Time
Site:	Crystal River
Issue date:	03/22/1989
From:	; FLORIDA POWER CORP.
To:	;
Shared Package
ML20246P721	List: 3F0389-18, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 166,removing cycle-dependent Core Operating Limits from Tech Specs & Relocating Limits to Core Operating Limits Rept; ML20246P724;
References
	NUDOCS 8903280302
	Download: ML20246P724 (40)
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9 INEEX DEFINITIONS SEcrIm ri a 1.0 DEFINITIONS (Cbntin_W)

WASTE GAS SYSTEM 1-6 VENTIIATICE EXHAUST TREAIMENT SYSTEM 1-7 IUBGE-RJRGING 1-7 VENTING 1-7 INDEPENDENT VERIFICATION 1-7 IlQUID RADWASTE TREA7 MENT SYSTEM 1-7 MEMBER (S) OF THE IUBLIC 1-8 I

SITE BOUNDARY 1-8 UNRESTRICTED AREA 1-8 CDRE OPERATDG LIMITS REPORP 1-8 OPERATIONAL MXES (TABIE 1.1) 1-9 FREQUENCY NOIATION (TABIE 1.2) 1-10 GYSIAL RIVER - UNIT 3 Ia As==ali=:nt No. g

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DEEINITICNS MEMBER (S) OF 'IEE WBLIC 1.37 MEMBER (S) OF 'IHE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.

'Ihis category shall include non-errployees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

'Ihis category shall H21; includo non-enployees such as vendiry machine servicemen or pen,L.n who, as part of their normal job function, evmionally enter an area that is controlled by the licensee for purposes of protection of individuals fr a exposure to radiation and radioactive materials.

SITE B00NIRRY 1.38

'Ibe SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

UNRES'IRICTED AREA 1.39 An UIncmICTED AREA shall be any area at or beyond the site boundary, amma to which is not u.ubulled by the licensee for purposes of protection of individuals frcm exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or industrial, ocumercial, institutional, and/or recreational purposes.

CORE OPERATING LIMITS maun 1.40

'Ibe OCRE OPERATING LIMITS REPORT is the unit specific rh'nant that provides core operating limits for the current reload cycle.

'Ihese cycle-specific core operating limits shall be determined for, each reload cycle in accordance with Specification 6.9.1.7.

Plant operation within these core operating limits is addr h in individual specifications.

Ag== du== it.[

CRYSIAL RIVER - UNIT 3 1-8

e REACTIVITY CIN1 POL SYSTDE MXERKKR TEMPERA'IURE mwFICIDTP LIMITING CCNDITION FCR OPERATION 3.6.1.3 h moderator temperature coefficient (MIC) shall be maintained within the acceptable limits provided in the CIRE OPERATING LIMITS REEORP.

APPLICMIII2TY: MXES 1 and 2*I.

ACTICE:

With the innaarator taperature coefficient outside the limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURWTTIANCE REQUIREMENTS 4.1.1.3.1

'Ihe MIC shall be determined to be within acceptable limits by con-b firmatory inaamirements. MIC inaamiM values shall be extrapolated and/or empensated to permit direct emparison with the limits.

l 4.1.1.3.2 h MIC shall be determined at the following frequencies and

'IHERMAL POWER Canditions during each fuel cycle.

Prior to initial operation above 5% of RATED 'IHERMAL POWER, a.

after eacit fuel loading.

b.

At any 'IHERMAL POWER, within 7 days after reactiing a RATED

'IHERMAL POWER equilibrium boran mwization of 300 ppn.

i "With K gg 2 1.0.

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ee Special ' Rest Excepticri 3.10.2 S

l CRYSIAL RIVER - UNIT 3 3/4 1-4 Assm2Esd.No.

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1 ACTION:

(Continued) c) A power distribution map is obtained frcan the incore detectors and Fg and F,NH are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and j

i d) The THERMAL POWER level is r*+M_ to $60% of the THERMAL

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POWER allowable for the reactor coolant pung ocanbination within one hour aryd within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the Nuclear Overpower Trip Setpoint is zwhvwl to 5 70% of the THERMAL POWER allowable for the reactor coolant punp combination, or e) The runninder of the rods in the group with the inoperable rod are aligned to within i 6.5% of the inoperable rod within one hour while maintaining the position of the rods within acceptable operating limits; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during anih=aqw=1t operation.

SURWTT.TANCE REQUIREMENTS 4.1.3.1.1 The position of each contrvl rod shall be determined to be within the group average height limits by ver!fying the individual red positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Asynenetric Rod Manitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each control rod not fitlly inserted shall be determined to be OPERABLE by movement of at least 3% in any one direction at least once every 31 days.

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CRYSTAL RIVER - UNIT 3 3/4 1-19 Au== mbud. No. [

REACTIVITY CONIROL SYS'IDE RDGUIATING ROD INSERrION LIMITS LIMITING CMDITION FER OPERATICH 3.1.3.6

'Ihe regulating rod groups shall be positioned within the acceptable '

operating limits for regulating rod position in the CNE OPERATING IlMITS REPORT.

APPLICABILITY: MXES 1* and 2*#

ACTION:

With the regulating rod groups inserted in the unacceptable operation a.

region, iwiately initiate and continue boration at greater than or equal to 10 GPM of 11,600 PIM boric acid solution or its equivalent, until out of the unacceptable operation region.

Additionally, either:

1. Restore the regulating groups to within the acceptable operating l

limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of hing the acceptable operation region, or

2. PMm 'IHERMAL POWER to less than or equal.to that fraction of RATED THERMAL POWER whidt is allowed by the red group position limits l

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of avr'aarting the acceptable operation region, or

3. Be in at least IUr STANDEN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of avr'aariing the acceptable operation region.

b. With the regulating rod groups inserted in the restricted operation regicr1 or with any group sequence or overlap outside the acceptable operating

limits, except for surveillance testing pursuant to Specification 4.1.2.1.2, either:

1. Restore the regulating groups to within the acceptable operating

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limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of avr==44ng the aw ioble operation region, or _ _

2. Parta 'INERMAL POWER to less than or equal to that fraction of RATED

'IHERMAL

POWER whidt is allowed by the rod group position limits l

l within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of avr'aariing the acceptable operaticri region, or

3. Be in at least IDF STANDEN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of hing the acceptable operation region.

"See Aparial Test Exceptions 3.10.1 and 3.10.2

With F gg greater than or equal to 1.0.

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g CRYSTAL RIVER - UNIT 3 3/4 1-25 AmendmentNos.Ati,g,JT,lg

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REACTIVITY CONIROL SYS'IDE REGUIATING ROD INSERPION LIMI'1_E SURVEIHANCE RWUIRDENIS 4.1.3.6

'Ihe position of each ra3ulating group shall be determined to be within the acceptable operating limits at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when:

a.

'Ihe regulating rod insertion limit alarm is incperable, then verify the groups to be within the insertion limits at least anoe per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; b.

The control rod drive sequence alarm is inoperable, then verify the groups to be within the sequence and cuerlap limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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NETIAL RIVER - UNIT 3 3/4 1-27 h nis t No.

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CN N RIVER - UNIT 3 3/4 1-30 W No.

3 REACTIVITY O2GOL SYSTDE POD PROGRAM IlMITING CINDITICH KR OPERATION 3.1.3.7 Eact1 ocritrol rod acuu=hly (safety, regulatirg ard APSR) shall be pro-1 ptwian=:d to operate in the core location and rod group specified in the CORE OPERATING IJMITS REPCRP.

APPLICABIIlTY: ICKES 1* and 2*.

ACTION:

i With any control rod not swicum 1 to opente as specified above, be in IUr STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEIIIANCE RB3JIRDENPS 4.1.3.7 a.

Each control rod shall be asennstrated to be programmed to aperate in the specified core position and rod group by:

l 1.

Selection and actuation frcan the u Lul roan and verifi-cation of movment of the proper rod as indicated by both the absolute and relative position indicators:

a)

For all control rods, after the control rod drive patcties are locked anhaarpant to test, iagwtaa.uing or maintenance within the panels, b)

For specifically affected indivirhW rods, followirq maintenance, test, Issu.section or unification of power or instrumentation cablos frun the wikvl red drive control system to the u Lul rod drive.

2.

Verifying that each cable that has been dir- -urund has been properly matched and reconnected to the specified control rod drive.

b.

At least anoe every 7 days, verify that the u Lul rod drive patch parmls are locked.

1 "See S-ial Test Exceptions 3.10.1 ard 3.10.2 s

GYSTAL RIVER - UNIT 3 3/4 1-33 Amerdment No.M

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CIESIAL RIVER - UNIT 3 3/4 1-34 Amendment No.

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REACTIVT1Y COMOL SYSTDE AXIAL POWER SHAPDC ROD DEERPION LIMTPS LIMITDG CONDITION FOR OPERATION 3.1.3.9 Except as requind for surveillance testing per Technical Specification 3.1.3.3, the axial power shaping rod (APSR) insertion limits shall be within the acceptable operatirq limits specified in the CDRE OPERATICNS LIMIT REPORT.

APPLICABILITY: ItXES 1 and 2*.

ACTION:

With the axial power shaping rod group outside the acceptable operatirg insertion limits, either:

a. Restore the axial power shaping red group to within the acceptable l

cperatirq limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b. Puhm THERMAL ICWER to less than or equal to that fraction of RATED THERMAL 10WER which is allowed by the rod group position limits l

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

c. Be in at least IDF STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REuin<uiENTS 4.1.3.9 The position of the axial power shaping rod group shall be determined to be within the acceptable cperating limits at least once every 12 l

hours.

With Keff 2 1.0.

d. Nos. h, yI, h, CRYSTAL RIVER - UNIT 3 3/4 1-37 Airri ^

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3/4.2 IMER DISIFTmrICN LIMPPS AXIAL POWER IMBAIANCE LIMITING ONDITICN FOR OPERATION 1

3.2.1 AXIAL POWER IMBAIANCE shall be maintained within the acceptable AXIAL POWER IMBAIANCE operating limits provided in the CORE OPERATING LIMITS REPORP.

APPLICABILITY: PO[E 1 above 40% of RATED THERMAL POWER *.

ACTION:

l With AXIAL IGER IMBAIANCE aMing the limits specified above, either:

)

a. Restore the AXIAL 30WER IMBAIANCE to within acceptable operating l

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limits within 15 minutes, or

b. Be in at least IDr STANDBY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEIII.ANCE REQUIREMENTS l

4.2.1 The AXIAL POWER IMBAIANCE shall be determined to be within acceptable

{

operating limits in endi core quadrant at least anoe every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40% of RATED 'IHERMAL ICHER avr=t when an AXIAL IOWER IMBAIANCE monitor is inoperable, then calculate the AXIAL POWER IMBAIANCE in each core quadrant with an inoperable monitor at least anoe per hour.

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" See F ial Test Exception 3.10.1 GYSIAL RIVER - UNIT 3 3/4 2-1 Amendment Nos. 4[ [, 1

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N SIAL RIVER - UNIT 3 3/4 2-3 Aff=:rdaust No.

m KHER DISIRIH7FIW LIMITS OuMRANT POWER TILT LIMITING OCNDITICH KR OPERATION 3.2.4

'IHE QUMEANT POWER TILT shall be maintained 5 the s mdy state limits e

fcr QUMRANT POWER TILT provided in the OCRE OPERATING LIMITS REPORP.

APPLICABILITY: MXE I abcra 15% of RATED 'IHERMAL IVWER.*

ACTION:

a.

With the QUMRANT POWER TILT determined to aw=ad the Steady State Limit but less than or equal to the Transient Limit in the cme OPERATICNS LIMITS REPORP.

1.

Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

a)

Either reduce the QUMEANI 10WER TILT to within its Steady State Limit, or b)

Badh r= 'IHERMAL POWER so as not to exceed 'INERMAL POWER, j

including power level cutoff, allowable for the reactor coolant pump ocanbination less at least 2% for endl 1% of QUMRANT POWER TILT in excess of the Steady State Limit and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the Nuclear Overpower Trip Setpoint and the Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBAIANCE Trip Setpoint at least 2% for endt 1% of QUMEANT POWER TILT in arr'a== of the Steady State Limit.

2.

Verify that the QUMEANI 10WER TILT is within its Steady State Limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after =w=ading the steady State Limit or reduce 'IHERMAL ICWER to less than 60% of

'IHERMAL POWER allowable for the reactor coolant punp ocabination within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to 5 65.5% of 'IHERMAL POWER allowable for the reactor coolant puup ocabination within the hext 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit con-diticr1 prior to increasing 'INERMAL POWER; mihaaryiant POWER OPERATIN above 60% of 'IHERMAL POWER allowable for the reactor coolant plup ocabination may guc.Ed provided that the QUMEANT POWER TILT is verified within its Steady State Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED 'IHEEMAL POWER.

"See F ial Test Exception 3.10.1 CRYSTAL RIVER - UNIT 3 3/4 2-8 Amendment No.

POWER DIS"IRIR7rION LIMITS LIMITING CONDITIN KR OPERATIN (Continued) b.

With the QUAIRANT POWER TIIIP determined to eynaai the Transient.

Limit but less than the Mavi== Limit in the ONE OPERATING LIMITS REPORP, due to misalignment of either a safety, regulating or axial power shaping rod:

1.

Parkrw 'INERMAL POWER at least 2% for each 1% of ' indicated QUAIRANT POWER TILT in excess of the Steady State Limit' within 30 minutes.

2.

Verify that the QUAIRANT POWER TILT is within its Transient Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after avnaa'iing the Transient Limit or rartirw 'IHERMAL POWER to less than 60% of 'IHERMAL POWER allowable for the reactor coolant punp ocabination within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to 5 65.5% of 'IHERMAL ICWER allowable for the reactor coolant punp ocabination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit can-dition prior to increasing 'IHERMAL POWER; mihaarymrit POWER OPERATICN above 60% of 'INERGAL POWER allowable for the reactor coolant punp ocanbinaticn may rvce 1 provided that the QUAIRANT POWER TIIlr is verified within its Steady State Limit at least anos per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED 'IHERMAL IVWER.

c.

With the QUAIRANT POWER TILT determined to exceed the Transient Limit but less than the Maximum Limit in the OCRE OPERATING LIMITS REPCRP, due to causes other than the miaal 4===d. of either a safety, regulating or axial power shaping rod:

1.

Parkrm 'IHEEMAL POWER to less than 60% of 'IMERMAL POWER allowable for the reactor coolant puup ocabination within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to $ 65.5% of 'IHEEMAL POWER allowable for the reactor coolant puup ocabinaticm within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.

Identify and correct the cause of the out of limit can-dition prior to increasing 'IHERMAL POWER; mihaarytarit POWER OPERATICE above 60% of 'IHERMAL POWER allowable for the reactor coolant pung ocabination may ed provided that the QUAIRANT 10WER TILT is verified within its Steady State Limit at least anoe per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED 'IHERMAL POWER.

CRYS'IAL RIVER - UNIT 3 3/4 2-9 Amendment No.

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l IOWER DISTRIHJPIN LIMPTS I

LIMITING CWDITICH FOR OPERATION (Continued) j ACTION:

(Continued) l d.

With the QUAIRANT POWER TILT detennined to avnaad the Maximam

)

Limit in the CORE OPERATING LIMITS REPORT, reduce THERMAL l

l POWER to 515% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEIIIANCE RDQUIRDENIS I

4.2.4 The QUAIEANT POWER TILT shall be determined to be $ the steady l

state limits at least once every 7 days durirg operation above 15% of RATED THERMAL IOWER except when the QUAERANT POWER TILT monitor is inoperable, then the QUAIEANT 10WER TILT shall be calculated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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N3 3/4 2-11 pg,

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3/4.9 REFUFTTNG OPERATIms Bof0N CONCENTRATION IJMITING CIEDITICH FOR OPERATION 3.9.1 With the reactor vamaal head unbolted or renoved, the boron con-centration of all filled portions of the Reactor Coolant Systen and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is net:

Either a K,llowance for uncertainties, orff of 0.95 or less, whicts includes a 1%

a.

servative a b.

A boren cua.askation 2 limit described in the ONE OPERATING LIMITS REIMT.

APPLICABILITY: MXE 6*.

ACTION:

With the requi-tus of the above specification not satisfied,. innediately suspend all operations involving CDRE ALTERATIONS or positive reactivity changes, and initiate and continue boration at 2 2700 gpn of 2270 ppn boron solution or its equivalent until Q ff is rMM to S 0.95 or the bortri wa->Lution is restored to 2 lims.t riammibed in the CNE OPERATING LIMITS l

REPORT, whichever is the are restrictive. The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4

4.9.1.1 The more restrictive of the above two reactivity canditions shall be determined, prior to:

a.

Renoving or unbolting the reactor vessel head, and b.

Withdrawal of any safety or regulating rod in excess of 3 feet frun its fully inserted position.

4.9.1.2 The boren cu->Lution of the reactor coolant systen and the refueling canal shall be determined by cf=W1 analysis at least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

1he reactor shall be maintained in MXE 6 whenever the reactor vessel head is unbolted or renoved and fuel is in the reactor vaaaal.

Q USTAL RIVER - UNIT 3 3/4 9 Amendment No.

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m AMINISIRATIVE CINIROIS MNIHLY OPERATING Mtluq 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be subnitted cm a monthly basis to the Director, Office of Inspection and Enfutuisir.:nt, U. S. Nuclear Regulatory hbion, Washington, DC 20555, with a copy to the Regional Office, subnitted no later than the 15th of each month followirg the calendar month covered by the report.

CORE OPERATING LIMITS xtaun 6.9.1.7 Core operatirg limits shall be established and h= anted in the OQRE OPERATDG IJMITS REERP before each reload cycle or any remaining part of a reload cycle for the following:

3.1.1.3 Moderator Temperature Ocefficient 3.1.3.6 Regulating Rod Insertion Limits I

3.1.3.7 Rod Pr% tam l

3.1.3.9 Axial Power Shaping Rod Insertion Ilmits 3.2.1 Axial Power Imbalance 3.2.4 Quadrant Power Tilt 3.9.1 Boron CtramuLration

'Ibe analytical methods used to determine the core cparating limits shall be those previously reviewed and approved by NRC in Topical Report BAR-10122A, Rev.1, " Normal Operating Cbntrols". 'Ihis report received NRC approval in Safety Evaluaticn Reports dated SepFamhar 14, 1979 and April 20, 1984. 'Ihe methodology for Rod Fr@ sam and Refuel Boron Otra.=id. cation received NRC approval in the Safety Evaluation Reported dated

'Ibe core operating limits shall be determined so that all applicable limits (e.g.,

fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. 'Ihe OCRE OPERATING LIMITS RENRP, incJuding any mid-cycle revisions or supplanents thereto, shall be provided upon issuance, for each reload cycle, to the NRC W= ant Ocotrol Desk with copies to the Regional Administrator and Resident Inspector.

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QESIAL RIVER - UNIT 3 6-15 AiisinJuant No.

3/4.2 POWER DISIRIIUTION 'm BASES

'Ihe specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:

(a) maintaining the minimJm INBR in the core within the limit during normal operation and during short term transients, (b) maintaining the peak linear power density $ 18.0 kw/ft durire normal operation, and (c) maintaining i

the peak power density $ 20.5 kw/ft durity short term transients. In addition, the above criteria must be met in order to meet the a==rtions used for the l

loss-of-coolant accidents.

h power-imbalance envelope and the insertion limit curves, defined in the CNE OPERATING LIMITS REPCRP (ODIR), are hnmad on I.DCA analyses which have l

defined the merium linear heat rate such that the moviam clad tarperature will not exceed the Final Acosptance Criteria of 2200*F following a I.OCA.

Operation outside of the power-imbalance envelope alene does not ocristitute a situation that would cause the Final Acceptance Criteria to be avemadad should a IDCA rvvw. h power-imbalance envelope Wu:E=uis the boundary of -

l operation limited by the Final Acceptance Criteria only if the w d.w l rods are at the insertion limits, as defined in the ODIR, arx1 if the steady state limit QUAIRANT POWER TILT exists. Additional conservatism is intrrv*vwi by application of:

a.

Nuclear uncertainty factors.

b.

'Ibermal calibration uncertainty.

l c.

Fuel densification effects.

d.

Hot rod manufacturing tolerance factors.

h conservative application of the above peaking augmentation factors l

considers the potential peaking penalty due to fuel rod blow, h ACTION statements whidi permit limited variations fran the basic requirements are w nied by additional restrictions which ensure that the original criteria are met.

h definitials of the design limit nuclear power peakirq factors as used in these specifications are as follows:

Fg Nuclear Heat Flux Hot Channel Factor, is defined as the mav4== local fuel rod linear power density divided by the averre fuel rod linear power density,===ing rxxninal fuel pellet and rud dimansicris.

CRYSTAL RIVER - UNIT 3 B 3/4 2-1 Amendment Nos.

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t" NWER DIFIRIBUI' ION LIMITS BASES Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of AH

-the integral of linear power along the rod on which min 12m2m INBR occurs to the average red power.

It has been determined by extensive analysis of possible operating power shapes that the design limits an nuclear power peaking and on miNnann INER at full power are met, provided:

Fg 5 3.13;

$ 1.71 AH Power Peaking is not a directly <,haanrable quantity and therefore limits have been established on the hamam of the AXIAL 10WER IMBEANCE prrvW by the power peaking.

It has been determined that the above hot channel factor limits will be met provided the following canditions are maintained.

1. Control rods in a single group move together with no individual rod insertion differing by more than 6.54 (indicated position) frai the group average height.

2. Regulating rod groups are sequenced with overlapping groups as required in Specificaticm 3.1.3.6.

3. 'Ihe regulatirg rod insertion limits of Specification 3.1.3.6 and the axial power shaping red insertion limits of Specification 3.1.3.9 are maintained.

4. AXIAL POWER IMBMANCE limits are maintained. 'IHE AXIAL MWER IMBMANCE is a waamwe of the difference in power between the top and battan halves of the core Calculations of core average axial peakirq factors'for many plants and mananinnents fran operating plants under a variety of operating canditions have been correlated with AXIAL POWER IMBMANCE. 'Ihe correlation shows that the design power shape is not er'aadai if the AXIAL POWER IMBMANCE is maintained within the limits defined in the CDIR.

'Ihe design limit power peaking factors are the most restrictive calculated at full power for the range fran all control rods fully withdrawn to minimum allowable nul rod insertion and are the core DGR design basis. 'Iherefore, for operation at a fraction of RAITD IHERIRL IWER, the design limits are met.

When using incore detectors to make power distribution maps to determine Fg and ETH:

'1h maamwement of total peaking factor, FgMeas, shall be incraaamd a.

by 1.4 percent to account for manufacturing tolerances and further inctumaai by 7.5 percent to at,rvunit for maamninnent error.

GYSIAL RIVER - UNIT 3 B 3/4 2-2 Amendment No.

e I:OWER DIFIRIH7FION LIMITS i

BASES b.

The maanienent of enthalpy rise hoc channel factor PDI, shall be inctmanari by 5 percent to arvvmint for naamninnent error.

For Candition II events, the core is protected frcan avr==iing allowable fuel -

melt limit locally, and frtan going belw minima allowable WBR by autanatic protection an power, AXIAL POWER IMBAIANCE, pressure and temperature. Only canditions 1 through 3, above, are mandatory since the AXIAL POWER IMBAIANCE is an e.xplicit input to the Reactor Protection Systen.

The QWGANT POWER TILT limit assures that the rarital power distribution satisfies the design values used'in the power capability analysis. Partial power distribution maamirements are made during startup testing and periodically during power operation. For QWGANT POWER TILT, the safety (maamninnent independent) limits for Steady State is 4.92, Transient State, and the Mav4==

Limit are defined in the ODIR.

The QWGANT POWER TILT limit at whicit corrective action is required provides IRB and linear heat generation rate protection with x-y plane power tilts.. The limit was selected to provide an allowance for the uncertainty maaminted with the power tilt. In the event the tilt is not corrected, the margin for uncertainty on Fg is reinstated by reducing the power by 2 peu.v L for each peux ut of tilt in excess of the limit.

3/4 2.5 INB PARAMETERS l

The limits on the IEB related parameters aanwe that eacts of the parameters are maintained within the normal steady state envelope of operaticri maannari in the transient and accident analyses. The limits are consistant with the FEAR initial assumptions and have been analytically demonstrated =iarriate to maintain a INER within the limit throughout endt analyzed transient.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters through instruaert roarienst j

is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient aparation. '!he 18 month periodic maanninnent of the RCS total flow rate is adequate to detect flw degadation arB' ensure correlation of the flw indicaticri channels with maamned flow sucts that the indicated p.u.v d. flow will prwide sufficient verification of flow rate an a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

i GYSTAL RIVER - UNIT 3 B 3/4 2-3 Amendment Nos.

1

l i

(

l ATTACHMENT 2 SAMPLE Core Operating Limits Report

/

i I

I FLORIDA POWER CORPORATION CRYSTAL RIVER 3 UNIT i

CYCLE 7 I

CORE OPERATING LIMITS REPORT REVISION 0 1

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1.0 Core Operating Limits This Core Operating Limits Report for CR3 Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The core operating limits have been developed using the methodology provided in the references.

The following cycle-specific core operating limits are included in this report:

1) Moderator temperature coefficient limits

2) Regulating rod insertion limits

3) Rod program group pcsitions

4) Axial power shaping rod insertion limits

5) Adal power imbalance operating limits

6) Quadrant power tilt limits and

7) Refueling boron concentration limits.

2.0 References

1. B&W Fuel Company, topical report BAW-10122A, Rev.1, " Normal j

Operating Controls,, May 1984,

2. B&W Fuel Company, topical report BAW-10118A, " Core Calculational Techniques and Procedures," December 1979.

3. B&W Fuel Company, topical report BAW-10152A, " NOODLE - A Multi-Dimensional Two-Group Reactor Simulator," June 1985.

4. Letter from to

, dated 1989. (NRC SER for Rod Program and Retuel Boron Concentration Methodologies) l l

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l Page 1 of 12 l

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Crystal River 3, Cycle 7 MODERATOR TEMPERATURE COEFFICIENT LIMITS The moderator temperature coefficient (MTC) shall be:

4 a.

Less positive than 0.9 x 10 Ak/k/*F whenever THERMAL POWER is < 95% of RATED THERMAL POWER, b.

Less positive than 0.0 x 10-4 Ak/k /*F whenever THERMAL POWEk is.>_95% of RATED THERMA [ POWER, and c.

Less ne tive than -3.0 x 104 Ak/k/*F at RATED THERMAL POWE i

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l These limits are referred to by Technical Specification 3.1.1.3 i

Page 2 of 12

. _ _ _ _. _ _ _ _ _ _ _ = _ - _ _

Crystal River 3, Cycle 7 Regulating Rod Group Insertion Limits for Four-Pump Operation From 0 to 500 + 10 EFPD 110 (200,102)

(300,102) 100

-(270,102)

(270,92) i 90 L

UNACCEPTABLE RESTRICTED y

80 OPERATION OPERATION (250,80) 2 l

70 SHUTDOWN y

MARGIN LIMIT 60

~

I 3

50 (120,50)

(175,50) e 40 x

ACCEPTABLE-2 OPERATION 30 20 (60,15) 10 (0,5)

O i'

0 50 100 150 200 250 300 Rod Index, % Withdra w 0

25 50 75 100 0

25 50 75 100 t

t 1

e I

t f

f f

f j

This figure Group 5 Group 7 referred to by Technical Specification 3.1.3.6 0

25 30 7,5 100 l

Group 6 Note 1:

A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Note 2:

This Figure shall be used up to complete APSR withdrawal per Technical' Specification 3.1.3.9.

Page 3 of 12 l

Crystal River 3 Cycle 7 i

I Regulating Rod Group Insertion Limits for Four-Pump Operation After 500 t 10 EFPO 110 (208,102)

(300,102),

(

02) 100 (250,92) gg UNACCEPTABLE OPERAT'ON RESTRICTED (250,80) u 80 y

OPERATION E

SHUTDOWN 70 MARGIN E

LIMIT 60 (127,50) 50 (175,50) l H

ACCEPTABLE 40 b

OPERATION 5

30 l

20 (54,15) i 10 (0,5) 1 0

1 0

50 100 150 200 250 300 l

Rod Index, i Withdrawn 0

25 50 75 100 0

25 50 75 100 t

t i

1 I

t t

f f

This figure Group 5 Group 7 referred to by Technical Specification 0

25 50 75 100 3.1.3.6 Group 6 Note 1:

A rod group overlap of 25 i 5% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Note 2:

This Figure shall be used after complete APSR withdrawal per Technical Specification 3.1.3.9.

Page 4 of 12 i

i

.i Crystal River 3, Cycle 7 j

j 1

Regulating Rod Group Insertion Limits for Three-Pump Operation From 0 to 500+10 EFpD 110 1

100 90

.(300,77) 80 b

UNACCEPTABLE (200,77)

(270'77) g OPERATION (270,69.5)

I,e 70 f

jg 60 RESTRICTED (250,60.5) l OPERATION l

?

SHUTDOWN i

MARGIN %

j y

50 LIMIT H

I 40 J

(120,38)

(175,3S) l y

j 5

30 l

ACCEPTABLE 20 OPERATION l

10 (60,11.75) 1 (0,4.25}

0 50 100 150 200 250 300 Rod Index, % Withdrawn l

0 25 50 75 100 0

25 50 75 100 f

referred to Group 5 Group 7 l

by Technical l

Specification 3.1.3.6 0

25 50 75 100 i

t t

i f

Group 6 Note 1:

A rod group overlap of 25 i S% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Note 2:

This Figure shall be used up to complete APSR withdrawal per Technical Specification 3.1.3.9.

l Page 5 of 12 I

Crystal River 3,~ Cycle 7 Regulating Rod Group Insertion Limits for Three-Pump 1

Operation After 500+10 EFP0 110 i

100 90 UNACCEPTABLE OPERATION

(300,77) 80 g

(208,77.)

(265,77) ^

^

x E

70 (260,69.5)

'l b

RESTRICTED (250,60.5) 60 OPERATION d

SHUTDOWN I

7 MARGIN 50 LIMIT c:

0 (127,38)

(175,38)

)

5' 30 ACCEPTABLE OPERATION 20 (64,11.75) 10 0

O 50 100 150-200 250 300 Rod Index, " Withdrawn 0

25 50 75 100 0

25 50 75 100 g

(

t 1

1 f

f 1

9 I

s f1 Group 5 Group 7 gg by Technical Specification 3.1.3.6 0

25 50 75 100-t f

I t

I Group 6 Note 1:

A rod group overlap of 2515% between sequential withdrawn groups 5 and 6. and 6 and 7 shall be maintained.

Note 2:

This Figure shall be used after complete APSR withdrawal per Technical Specification 3.1.3.9.

Page 6 of 12

Crystal River 3, Cycle 7 Control Rod Locations and Group Designations Fuel Transfer l

Canal

?

A 1

6l 1l B

3 5

5l l3 l

C D

7 8'

7l 8

7 3

5 4

4 5

3 E

F 1

8 6

2 l6l 8

1 G

5 4

2 2

l4 5

l2l l7 6

Y H

w-6 7

2 K

5 4

2 2

l4-l 5

L.

l1 8

6l 2

l6l 8

1 4l l5 l 3

M

-l 3 l5 4

N l

7 8

7l l8 7

l l

3 5

5l l3 0

P l

l l

1 6

l1l l

l l

l t

i R

I 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15,

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X Group Numoer Grouc No. of Reds Function l

1 8

Safety l

2 8

Safety 3

8 Safety 4

8 Safety 5

12 Control This figure 6

8 Control 7

8 Control referred to 8

8 APSRs by Technical Specification Total 68 3.1.3.7 Page7 of 12

q a

4 Crystal River 3, Cycle 7 AXIAL POWER SHAPING ROD INSERTION LIMITS Up to 490 EFPD, the APSRs may be positioned as necessary. The APSRs shall be completely withdrawn (100%) by 510 EFPD. Between 490 and 510 EFPD, the APSRs may be withdrawn. However, once withdrawn during during this period, the APSRs shall not be reinserted.

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These limits are referred to b Technical y

Specification 3.1.3.9 1

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. Page 8 of 12 L

V 1

Crystal River 3, Cycle 7 Axial Power Imbalance Envelope for Four-Pump Operation From 0 EFPO to EOC 4

110 --

i l

(-20,102)

(15,102) 100-1 I

(-25,92)

(15,92)

)

4 90-

,(20,80)

(-28,80)<

80 -

70 -

b

$ 60 ~

c-(-28,50) o E 50 -

'(20,50) e

5 ACCEPTABLE UNACCEPTABLE e 40

. OPERATION OPERATION 3

aw 30 - -

I b

j 20-

)

10 -

)

j 0

i

-50

-40

-30

-20

-10 0

10 20 30 40 50 Axial Power Imbalance, I j

This figure referred to by Technical Specification 3.2.1 i

Page 9 of 12 l

Crystal River 3, Cycle 7 Axial Power Imbalance snvelope for Three-Pump Operation From 0 EFPO to EOC 110--

100- -

90-(-20,77)-

(15,77)

(-25,69.5) 70.

(15,69.5)

(-28,60.5)'

60

,(20,60.5) bx E 50- -

E' 40.

.E o(20,38)

(-28,38) o ACCEPTABLE UNACCEPTABLE 330- 0PERATION OPERATION E

w, 20 U

1 5

1 c-10" -

u.,,

0 i

-50

-40

-30

-20

-10 0

10 20 30 40 50 Axial Power imoalance, %

This figure referred to by Technical Specification 3.2.1 1

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Page 10 of 12

,,. '~

se Crystal River 3, Cycle 7 QUADRANT POWER TILT LIMITS i

1 STEADY STATE TRANSIENT MAXIMUM

{

LIMIT LIMIT LIMIT OUADRANT POWER TILT as measured by:

SymmetricalIncore 4.12 10.03 20.0 Detector System

]

l Power Range Channels 1.96 6.96 20.0 Minimum Incore 1.90 4.40 20.0 Detector System Measurement Independent 4.92 11.07 20.0 This table is referred to by Technical Specification 3.2.4 1

c Page 11 of 12

d Crystal River 3, Cycle 7 I

l REFUELING OPERATIONS BORON CONCENTRATION The boron concentration in the fuel transfer canal and the spent fuel pool must be greater than the minimum required for refueling, which is 2520 ppm PLUS 1.5 ppm for each EFPD cycle 6 operates for less than 435 EFPD.

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This concentration is referred to by Technical Specification 3.9.1 l

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l Page 12 of 12 1

1

ML20246P724

Text

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