ML18005B088

Proposed Tech Specs Re Cycle 3 Reload & Rev to Min Containment Backpressure Calculation

ML18005B088
Person / Time
Site:	Harris
Issue date:	10/02/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005B087	List: ML18005B086 ML18005B088
References
NUDOCS 8910060186
Download: ML18005B088 (10)

Text

ATTACHMENT 2 TO NLS-89-252 REVISED TECHNICAL SPECIFICATION PAGES 89i0060186 85'1002 PDR ADOCK 05000400 P PDC

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';1 SAFETY LIHITS BASES 2.1.1 REACTOR CORE

~graf Qj'ITH A.ITACHFO INCAN'RT cricciona of this a ety over eating of the fue nd poa-sib ding vhich vouam'erforation t in the reLeaae of ' f prod-ucts t re actor coolant. Ove Ln he fuel cladding evanted by rescr1ctL L operation to n the nu boiLing r e re the heat tranafe ficient ' and the c L aurfa pe ra'c ure is slightly above ool uration temperatu Operation above boundary of the nucleat regime could result 1 excessive g c cures because of set aperture from nu-boy ) and ultant ahar et ion in tranafer coeffi-ci t dirac tl urabl>> te r during o 'on and there-for 1

no PS'nd a

h L ough the M-3 rea ctor corre t rtu a re and pres s u'r The M-3 NI correlati been r-oped di ct the DMS fl ocation of M for axial and nonunifo flux di at r nay oeal NI heat flux r is defined as t of lux that vould

'o cuLated particular core lo actuaL Local lux and i ative 0 the margin to DN.

The minimum vaL ue e rl'ng steady-state o normaL operationa transients, an cipated nts ia Limite ia value corre-sponds to a obability at eonfiden chat 'll not occur and is e s an appropriace ma 0 all operacin iclona ~

The of Figure 2.1-1 shov the inca of TH&MAL POMEk, toe C System pressure and avera e for vhich the minimum 's aa than 1.30, or the aver Lpy a e veaseL exit ia equal t nthaLpy of urated liquid.

l gg,@or These curves are based on an enthaLyy hot channel factor, F>~, of and a t OPAL Cual reference cosine vith ~ peak of 1.55 for~iaL paver shape. An alLovance ia VRN TAG' included for an increase in calcul.ated P>~ at reduced pover baaed on the Rail expression!

LC2

[1 + 4.3 (1-4)] gyes LOPAR +~~p ~nd Share P is the fraction of RATED TliEIL POMER.

Thea>> limiting heat flux conditions are higher than those calcuLated for the range of aL1 control rods fully vithdravn to the maxi'lLovable control rod insertion assuming the axiaL pover iabalance is within the Limits of the fl (hI) function of the Overceaperacure trip.'hen the axial pover imbalance is noc vithin che tolerance, the axial pover imbalance effect on the Over-tamyerature hT crips vill reduce che Setyoints to provide yrotection consistent with cor f t imi f

F>H -I.LS >+ o.3S t'.I-P)34r N<TA

~<u'HEARON HARRIS - UNIT 1 8 2-1 Amendment No

REACTIVITY OL SYSTEMS 3/4 ~ 1 ~ 3 MOVABLE CONTROL ASSEMBLIES CROUP HEICHT LIMITINC CONDITION FOR OPERATION 3,1.3,1 All shutdovn and concroL rods shaLL be OPERABLE and positioned vichin 12 steps (indicaced position) of their group seep councer demand position.

APPLICABILITY: MODES 1<<and 2<<.

ACTION:

a~ With oae or more rods inoperabLe due to being iassovable as a resulc of excessive friction or,. mechanical interference or knovn to be uncrippable, determine that the SHUTDOWN MARCIN requirement of Specification 3.1.1.1 is satisfied vichin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY Mithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

n

b. Mich more than one rod misaligned from che group step counter demand position by mora than + 12 steps (indicated position), be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ~

c~ With more, than one rod inoperabl.e, due co a rod control urgent failure alarm or obvious electrical problem ia the rod controL system existing for greater thaa 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, be in HOT STANDBY vithia the fol.loving 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> With one rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligaed from ics group step counter demand heighc by more than + 12 steps (indicaced position),

POMER OPERATION may continue provided chat vithin 1 hour:

1 ~ The rod is restored to OPERABLE status vithin the above alignment requirements o oc 2m The rod ii declared iaoperable and the remainder of the rods in the group vith the iaoperable rod are aligned to vichia + 12 steps of the inoperable rod vhiLe maintaining the rod sequence on cordrpl honks shal be rescr]cted pursuant to Specificatioa 3.1.3.6 during apccif'ied tn We subsequent operatioay or g~ OplLAAQ g('mirb RePov+, 3~ The rod is declared inoperabLe and the SHUTDOWN MARCIN requirement of Specification 3.1.1.1 is sacisfied. POMER OPERATION may thea 'continue provided that:

a) A reevaluation of each accident analysis of Table 3.1"1 is performed vichin S days[ this reevaluation shaLL confirm chat th>> previously analyred results of these accidents

<<See Special. Test Ezceptions Specifications 3.10.2 and 3.10.3 ~

SHEARON HARRIS'NIT 1 3/4 1-14 Amendment Nn. g

n 3/4.2 POSER DISTRIBUTION LIMITS, 3/4.2 ' AXIAL FLUX DIFFERENCE LIMITINC CONDITION FOR OPERATION 3.2.1 The indicated AXIAL-FLUXDIFFERENCE (AFD) shaLL be maintained within:

a. the accepcabLe operational space 0 AxiaL Offsec ControL (RAOC) operacion, o aS S~iFfed in +e &re QerW~

l.irni4s A e porI be within a about e tar t AFD during Base Los operatio aS Speci@'ed in We Core OperaHng LimiB Re ort:

APPLICABILITY! MODE 1 above 50Z of RATED THERMAL PNER+.

ACTION:

a For operation with the indicated outside of the 4l,+ 8pM il

~ RAOC AFD

1. Restore th>> indicated within 1S minutes, or AFD to withi e 'imits 5pcci~ied jn Qe Q0rc Qpercdj RA Qntits gapo

2. Reduce THERMAL POWER to Less than 50X of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip setpoints to Less than or equal to SSX of RATED

'DERMAL POSER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

be For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target AFD, either!

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1. Restore the indicated AFD to within the target band Limits within 15 minutes, or

2. Reduce THERMAL POMER to less than APL of RATED THERMAL POWER and discontinue Base Load operation within 30 minutest C ~ THERMAL POSER shall not be increased above 50Z of RATED THERMAL speci/led tdtWc Core OporaHg p;rdti+S pICFIor+ for RAOC Ope,r4bort I

+See SpeciaL Test Exception 3.10.2

~APL is the minimum allowabLe power LeveL for Base Load operation and will be provided in the per Syecificacion 6.9 '.6 ~

5 ~oP~a~v 'zP p'""

SHEARON HARRIS - UNIT 1 3/4 2-1 Amendment Nn.+

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES

. GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All shutdown and control rods shall be OPERABLE and positioned within

+ 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY: MODES 1 and 2 ACTION:

a 0 With one or more rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours.

b. With more than one rod misaligned from the group step counter demand position by more than + 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

C ~ With more than one rod inoperable, due to a rod control urgent failure alarm or obvious electrical problem in the rod control system existing for greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d. With one rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than + 12 steps (indicated position),

POWER OPERATION may continue provided that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />'.

1. The rod is restored to OPERABLE status within the above alignment requirements, or

2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits on control banks specified in the Core Operating Limits Report. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or

3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents See Special Test Exceptions Specifications 3.10.2 and 3 '0.3.

SHEARON HARRIS UNIT 1 3/4 1-14 .Amendment No.

4 2.1 SAFETY LIMITS BASES 2.1.1 REACTOR CORE (Continued)

These curves are based on an enthalpy hot channel factor, F , of 1.62 for LOPAR fuel and 1.65 for VANTAGE 5 fuel and areference cosine with a peak of 1.55 for axial power shape. An allowance is included for -an increase in calculated F<H at reduced power based on the expression:

F<H

= 1.62 [1 + 0.3 (1-P)] for LOPAR fuel, and F<H

= 1.65 [1 + 0 '5 (1-P)] for VANTAGE 5 fuel Where P is the fraction of RATED THERMAL POWER.

These limiting heat flux conditions are higher than those calculated for the range of all control rods fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the limits of the fl (AI) function of the Overtemperature trip. When the axial power imbalance is not within the tolerance, the axial power imbalance effect on the Over-temperature AT trips will reduce the Setpoints to provide protection consistent with core Safety Limits.

SHEARON HARRIS UNIT 1 B 2-la Amendment No.

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within'.

II

a. the acceptable operational space as specified in the Core Operating Limits Report for Relaxed Axial. Offset Control (RAOC) operation, or

b. within a band about the target AFD during Base Load operation as specified in the Core Operating Limits Report.

APPLICABILITY: MODE 1 above 50X of RATED THERMAL POWER>'<.

ACTION:

a ~ For RAOC operation with the indicated AFD outside of the limits specified in the Core Operating Limits Report, either:

1 ~ Restore the indicated AFD to within the limits specified in the Core Operating Limits Report within 15 minutes, or

2. Reduce THERMAL POWER to less than SOX of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux High Trip setpoints to less than or equal to 55%%d of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target AFD, either:

1. Restore the indicated AFD to within the target band limits within 15 minutes, or

2. Reduce THERMAL POWER to less than APL of RATED THERMAL POWER and discontinue Base Load operation within 30 minutes.

C ~ THERMAL POWER shall not be increased above 50X of RATED THERMAL POWER unless the indicated AFD is within the limits specified in the Core Operating Limits Report for RAOC operation.

'<See Special Test Exception 3.10.2

>'<>'<APL i's the minimum allowable power level for Base Load operation and will be provided in the Core Operating Limits Report per Specification 6.9.1.6.

SHEARON HARRIS UNIT 1 3/4 2-1 Amendment No.

DISTRUBITION CDocket F~ile, Shearon Harris Plant PAnderson DOCKET NO(S) 50-400 Hr. Lynn M. Eury Executive Vice President Power Supp1y Caro1ina Power 8 Light Company Post Office Box 1551 Ra1eigh, North Carolina 27602

'HEARON HARRIS NUCLEAR POllER PL'ANT, UNIT 1

. The following documents concerning our review of. the subject facility are transmitted for your information.

DESCRIPTION OF DOCUMENT - '.DATED Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.

Environmental Assessment and Finding of No Significant Impact.

Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nificant Hazards Conditions See Page(s)

Exemption Construction Permit No. CPPR- , Amendment No.

Facility Operating License No. ,Amendment No.

Order Monthly Operating Report for transmitted by Letter Annual/Semi-Annual Report:

transmitted by, Letter Other Office of Nuclear Reactor Regulation

Enclosures:

As Stated cc:See next page OFFICE> PDI I-1 "

'PA'n'd'e'rso'n""

SURNAME~

OATeg 9(29/89 .

NRC FORM 3ta tto/eo) NRCM 0240 OFFICIAL RECORD COPY