Text

Amends 154 & 31 to Licenses DPR-66 & NPF-73,respectively, Revising Tech Specs by Replacing cycle-specific Parameter Limits W/Ref to Core Operating Limits Rept
	ML20042F061
Person / Time
Site:	Beaver Valley
Issue date:	04/26/1990
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20042F062	List: ML20042F061; ML20042F064;
References
	DPR-66-A-154, NPF-73-A-031 NUDOCS 9005070173
	Download: ML20042F061 (45)
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UNITED STATES

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5 WASHING TON, D. C. 20665 NUCLEAR REGULATORY CuMMISSION

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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY i

PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVERVALLEYPOKERSTATION,UNITNO.],

AMENDMFNT TO FACILITY OPERATING LICENSE Amendn.ont t!o. ha License No. DPR 66 1.

The P!uclear Regulatory Ccemission (the Comission) has found that:

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A.

The application for amendnent by Duquesne Light Company, et al.

(thelicensee)datedDecember 14, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's ruler e d regulations set forth in 10 CFR Chapter It B.

The facility will oserate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Comission;-

i C.

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wil1 be conducted in compliance with the Comission's regulations; i

D.

The issuance of this amendment will net be inimical to the comon defense and security or to the health and safety of the public; and L

E.

The issuance of this emendment is in accordance with 10 CFR Part l

l 51 of the Comission's regulations and all applicable requirements have been satisfied.

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9005070173 900426 1

L PDR ADOCK 05000334 1:

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2.

Accordingly, the license is amended by changes to the Te dnical Specifications as indicated in the attachment to this license t

amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.154, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on issuance.

FOR THE NUCLEAD REGULAJORY COMMISSION b

W 5

Jo

. Stolz, ector Project Directorate I-4 Division of Reactor Projects I/I!

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

April 26,1990 p.

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c' ATTACHMENT TO LICENSE AMENDMENT NO. 154 FACIL17Y OPERATING LICENSE NO. NPR-66 DOCKET NO. 50-334 ReplacethefollowingpagesofAppendixA(Technicalspecifications)withthe enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change, Remove Pages Insert Pages 1

18 1-8 3/4 1-18 3/4 1-1B 3/4 1-19 3/4 1-19 3/4 1-23 3/4 1-23 3/4 1 23a 3/4 1-23a 3/4 1-24 3/4 1-25 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 a

3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-5 3/4 2-5 3/4 2-6 3/4 2-6 3/4 2-6a 3/4 2-6a 3/4 2-7 3/4 2-8 3/4 2-8 B3/4 2-1 B3/4 2-1 B3/4 2-?

B3/4 2-2 B3/4 2-4 B3/4 2-4 B3/4 2-5 B3/4 2-5 6-22 6-22 6-22a I

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i 1.0 DEFINITIONE (Continued) i 2)

Major changes in the design of rarlwaste treatment systems.

l (11guid, gaseous and solid) th:1.t could significantly increase the quantities or activity of effluents released or volumes of solid waste stored or shipped offsite from those previously considered in the FSAR and SER (e.g., use of asphalt system in place of cement);-

1 3)

Changes in system dasign which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that.would alter the curies released); and 4)

Changes' in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate shielding provisions).

l M_rMBERfSi OF THE PUBLIC i

1.36 MEMBERS OF THE PUBLIC shall include all persons.who are not occupationally associated with the plant.

This category dcas nJc-include employees of the

utility, its contractors or its vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries and persons who traverse portions of the site as the consequence of a public highway, railway, or waterway located within the confines of the site bcandary.-

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

CORE OPERATING LIMITS REPORT 1.37 The CORE OPEK\\ TING LIMITS REPORT (COLR) is the' unit-specific document that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating limits shall be determined, for each reload cycle in accordance with Specification 6.9.1.14.

Plant operation within these operating

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limits is addressed in individual specifications.

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BEAVER VALLEY - UNIT 1 1-8 A,mendment No.9hi,154

.o REACTIVITY CONTROL SYSTEMS

- a 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 8

GROUP HEIGHT i

LIMITING CONDITION FOR OPERATION i

3.1.3.1 All-full length shutdown and control rods shall be OPERABLE and positioned within 12 steps (indicated position, as determined in accordance with Specification 3.1.3.2) of their group step counter demand position.

I APPLICABILITY:

MODES 1* and 2*

ACTION:

i a.

With one or more full length rods inoperable due to-being L

immovable as a

result of excessive friction or mechanical 1

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full length rod misaligned from its group step counter demand position by more than 1

12 steps (indicated position determined in accordance with Specification 3.1.3.2), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c.

With one full length rod trippable but inoperable due to causes other than addressed by ACTION a above, or misaligned i

from its group step counter demand position by more than 12 j

steps (indicated position determined in accordance

. ith w

Specification 3.1.3.2), POWER OPERATION may continue provided that within one hour either:

1.

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

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The rod is declared inoperable and the remainder of~the I

rods in the group with the inoperable rod-are aligned to within 1 12-steps of the inoperable rod while maintaining the rod sequence and insertion limits provided in the CORE OPERATING LIMITS REPORT.

The THERMAL POWER level i

shall be restricted pursuant to specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN L

requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

The THERMAL POWER level is reduced to less than or equal to 75%

of RATED THERMAL POWER within the hour

and, within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high. neutron flux trip setpoint is reduced to less than or equal to 85%

of RATED THERMAL POWER.

BEAVER VALLEY-UNIT 1 3/4 1-18 Amendment No. %, M 1 M

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1 LIMITING CONDITION FOR OPERATION (C:ntinuOd) l b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once.per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) A power distribution map isobtajnedfromthemovable incere detectors and TQ(2) and To H are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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d) 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 i

accidents remain valid for the duration of operation under these conditions.

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d. With more than one rod tripable but inoperable due to causes other than addressed by Action a above, POWER-OPERATION.may l

continue provided that:

1. Within one

hour, the remainder of the rods in the bank (s)

I with the inoperable-rods-are aligned to within i 12 steps of the inoperable rods:while maintaining the rod sequence and insertion limits provided in the CORE OPERATING LIMITS REPORT.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and

2. The inoperable-rods are restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2 SURVEILLANCE REQUIREMENTS l

4.1.3.1.1 Each shutdown and control rod not fully inserted in the core shall be determined to be OPERABLE-by movement of at least 10 steps in any one direction at least on per 31' days.

4.1.3.1.2 The position of each full length red shall be determined

-to be within i

12 steps of the associated group demand counter by verifying the individual rod position at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months c

except during intervals when the Rod Position Deviation monitor is inoperable, then verify the group position at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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See Special Test Exception 3.10.2 and 3.10.4 9

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BEAVER VALLEY - UNIT 1 3/4 1-19 Amendment No. W. W.154

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I REACTIVITY CONTROL SYSTEM SMUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be within the insertion limits i

specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY:

MODES 1* and 2*#

ACTION:

i With a

maximum of one shutdown rod inserted beyond the insertion l

limit, except. for surveillance testing pursuant to Specification 4.1.3.1.1, within one hour either:

a. Restore the rod to within the limit, or I

b.. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS i

4.1.3.5 Each shutdown rod shall be determined to be within the l

insertion limit by use of the group demand counters, anc verified by the analog rod position indicators **

a. Within 15 minutes prior to withdrawal of any rods in control banks A,

B, C or D during an approach to reactor criticality, and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

See Special Test Exception 3.10.2 and 3.10.4.

- For power levels below 50% one hour thermal " soak time" is permitted.

During this soak time, the absolute value of rod motion is limited to six steps.

With Keff 21.0.

BEAVER VALLEY - UNIT 1 3/4 1-23 Miendment No.9H 154 I

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REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS 1

LIMITING CONDITION TOR OPERATION

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l 3.1.3.6 The control banks shall be within the insertion limits specified in the CORE OPERATING-LIMITS REPORT.

APPLICABILITY:

Modes 1* and 2*$

ACTIONt-With the corstrol banks inserted beyond the insertion limits, except l

for surveillance testing pursuant to Specification 4.1.3.1.1, either:

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a. Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b. Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to t

that fraction or RATED THERMAL POWER which is allowed by the t

bank position insertion limits specified in the CORE OPERATING l

LIMITS REPORT, or

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

i SURVEILLANCE REQUIREMENTS J

4.1.3.6 When the Rod' Insertion Limit Monitor is OPERABLE, the deviation between the position indicated by the individual analog rod l

position instrument channel and the position indicated by the corresponding group demand counter shall be checked ** iaanuall'y for each rod at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When the Rod Insertion Limit Monitor is inoperable, the deviation between indicated positions shall be checked ** manually at least once per 4 hoars, l

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I' See Special Test Exception 3.10.2 and 3.10.4 I

with K ff 2 1.0

- For pow,er lev,els below 50%, one hour thermal " soak time" is permitted.

During this soak time, the absolute value of rod motion is limited to six steps.

BEAVER VALLEY - UNIT 1 3/4 1-23a Ameninent No.-M, 154 l

(next page is 3/4 2-1) l I

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.g 3/4.2 POWER DISTRIBUTION LIMITS I

i AXIAL FLUX DIFFERENCE (AFD)

LIMITING CONDITION FOR OPERATION

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'l 3. 2.1, The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained l

within the target band specified in the CORE OPERATING LIMITS REPORT (COLR).

i APPLICABILITY:

MODE 1 ABOVE 50% RATED THERMAL POWER

l ACTION:

A. With the' indicated AXIAL FLUX DIFFERENCE outside of the target band and with THERMAL POWER:

1. Above 90% of RATED THERMAL POWER, within 15 mint:es:

l a) Either restore the indicated AFD to within the target band limits, or b) Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

2.

Between 50% and 90% of RATED THERMAL POWER:

a) POWER OPERATION may continue provided:

1) The indicated AFD has not been outside of the target l

band for more than 1

hour penalty deviation cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2) The indicated AFD is Within the target band.

Otherwise, reduce THERMAL-POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to s 55%

of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b) Surveillance testing of the Power Range Neutron Flux-Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained i

within the limits.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be l

i accumulated with the AFD outside of the target band during this testing without penalty deviation.

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See Special Test Exception 3.10.2 i

BEAVER VALLEY - UNIT 1 3/4 2-1 Amendment No. 'A'92,154 i

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'. ', '. POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) n s.

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b. THERMAL POWER shall not be increased above' 90%

of RATED THERMAL POWER unless the indicated AFD is within the target l band and ACTION a.2.a) 1), above has been satisfied.

c. THERMAL POWER shall not be increased above 50%

of RATED THEP. MAL POWER unless the indicated AFD has not been outside of the target band for more than 1

hour penalty deviation l cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS

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4.2.1.1 The indicated AXIAL' FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15%'of RATED THERMAL POWER by:

F

a. Monitoring the indicated AFP for each OPERABLE excore channel:

1. At least once per 7

days when the AFD Monitor Alarm is OPERABLE, and

2. At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status.

b. Monitoring and logging the indiented AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at.least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, t

when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding. each logging.

4.2.1.2 The indicated AFD shall be considered outside of its target l

band when-at least 2

of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

POWER OPERATION outside of the target band shall be accumulated on a time basis of:

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a. One minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and

b. One-half minute penalty deviation for each one minute of POWER l

OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

BEAVER VALLEY - UNIT 1 3/4 2-?

Amendment No. %W,%,154 l

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,a M DISTRIBUTTOtl LIMITS

'URVEILLANCE REQUIREMENTS (Centinund)

S 4.2.1.3 The target flux difference of each OPERABLE excore channel shall' be determined by measurement at least once por 92 Effective Full Power Days.

The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4.2.1.3 above or by linear interpolation between the most recently measured value and the design end-of-cycle value.

The provisions of specification 4.0.4 are not applicable.

I BEAVER VALLEY

UNIT 1 3/4 2-3 ll (Next page is 3/4 2-5) 1I I

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c' POWER DISTRIBGTION LIMITS HEAT FLUX HOT CMANNEL FACTOR-F (Z) g LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships:

g F (Z) $ [CIQ) [K(Z)) for P >0.5 l

g P

l T (Z) $ (CIQ) [K(Z)) for P 10.5 g

0.5

ern:

CFQ = The FQ limit at RATED THERMAL POWER j

prreided in the CORE OPERATING LIMITS REPORT, K(Z) = The normals.;ed FQ(2) as a function of core height provided in the CORE OPERATING LIMITS REPORT, and P = IHEEdbL POWER RATED THERMAL FOWER 2

AEELICABILITY:

MODE 1 i

ACTIOl{:

With FgiZ) 3xceeding its 11rit:

a. Reduce THERMAL POWER at least it for each 1% Fo(Z) exceeds the limit within 1b minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the overpower t T Trip Setpoints have been reduced at least 1% for each 1%

Fn(Z) exceeds the limit.

The Overpower a T Trip Setpoint Peduction shall be performed with the reactor suberitical.

b. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER: THERMAL POWER may then be.

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increased provided Fg(Z) is demonstrated through incore mapping to be within its limit.

BEAVER VALLEY - UNIT 1 3/4 2-5 Amendment No. %%,15?

-POWER'DISTPIBUTION LIMITS SURVEILIANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F

shall be evaluated to determine if F (Z) is within iN limit by:

g

a. Using the movable incore detectors to obtain a.

power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. Incraasing the measured F

component of the power distribution map by 3% to accoEnt for manufacturing tolerances x

and further increasing the value by 5%

to account for measurement. uncertainties, C

c. Comparing the F computed (Fxy ) obtained in b, above tot xy

1. The approprI. limitsatemeasuredcoreplanesgivenineandYYbelow, and F

for RATED THERMAL POWER (F

)

for the x

2. The relationship:

F xh = FTy

[1+PFXY(1-P))

l P

where F h

xy is the limit for fractional THERMAL POWER operation expressed as a function of F E, PFXY is the Power Factor multiplier for F provided in the CORE xy OPERATING LIMITS REPORT, and P is the fraction of RATED THERMAL POWER at which T was measured.

xy

d. Remeasuring F according to the following schedule:

xy isgreaterthantheF]y

1. When F limit for the xy L

appropriate measured core plane but less than the.Fxy relationship, additional power distribution maps shall be taken and*F compared to F xy xy and F,gy:

a) Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATEp THERMAL POWER or greater, the THERMAL POWER at which T was last determined, or xy b) At least once per 31 EFPD, whichever occurs first.

BEAVER VALLEY - UNIT 1 3/4 2-6 Amendment No. %, 154

3 POWER DISTRIB19 TION LIMITS

' SURVEILLANCE REQUIREMENTS (continued)

2. When-the F

is less than or equal to the FyP limit for xy the appropriate measured core

plane, additional power c

distribution maps shall -be taken and F

compared to P

L xy Ffy and F at least once per 31 EFPD.

xy (F *y

)~shall be

e. The F

limit for Rated Thermal. Power xy x

provided for all core planes containing bank "D" control rods and all unrodded core planes in the CORE OPERATING LIMITS REPORT.

f. The F

limits of e,

above, are not applicable in the xy following core plane regions as measured from the bottom of the fuel:

1. Lower core region from 0 to 15%, inclusive.

2. Upper core region from 85 to 100%, inclusive.

3. Grid plane region 12%

of core height (12.88 inches) measured from grid centerline.

4.

tere plane regions within 2% of core height ( 2.88 inches) about the bank demand position of the bank "D" control rods.

C L

g. With F

exceeding F

the effects of F

on F

xy xy, xy q -(Z) shall be evaluated to determine if F

(Z) is within its g

limit.

4.2.2.3 When F

(2) is measured pursuant to-Specification q

4.10.2.2, an overall measured Fg (Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

BEAVER VALLEY - UNIT 1

-3/4 2-6a A nondment I o. iW WC,154 (Next page is 3/4 2-3) l

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POWER DISTRIBUTION LIMITS

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NUCLEAR ENTHALPY HOT CHANNEL FACTOR - FN g LIMITING CONDITION FOR OPERATION N

3.2.3 F

shall be limited by the following relationship:

3 N

F

$ CFDH [1 + PFDH (1-P))

N where:

CFDH = F limit at RATED THERMAL POWER i

provide n the CORE OPERATING LIMITS REPORT, j

PFDH=ThePowerFactormultiplierfor.F$g i

provided in the CORE OPERATING LIMITS REPORT, and i

P = THERMAL POWER RATED THERMAL POWER APPLICABILITY:

MODE 1 ACTION:

WithThexceedingitslimits:

a. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER i

within 2

hours and reduce the Power Range Neutron Flux-High Trip Setpoints to S 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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b. Demonstratethruin-coremappingthatThiswithinitslimit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c. Identify and correct the cause of the out of limit condition prior to increasing THERMAL OWER, subsequent POWER OPERATION-may proceed provided that F,,nis demonstrated through in-core mapping to be within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL power, at a nominal 75%

of RATED THERMAL' POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95% or greater RATED THERMAL POWER.

BEAVER VALLEY - UNIT 1 3/4 2-8 Amendaent No. S. K 154 1

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3'/4.2 POWER DISTRIBUTION LIMITS BASES The 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 minimum DNBR in the core greater than or equal to the design DNBR limit during normal operation and in short term transients, and (b) limiting the fission-gas release, fuel pellet temperature & cladding mechanical properties to within assumed design -criteria.

In addition, limiting'the peak linear power density.during condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.

The definitions of hot channel factors as used in these specifications are as follows:

Fg(Z)

Heat Flux Hot Channel

Factor, is defined as the maximum local heat flux _ on the surface of a

fuel' rod at core elevation Z

divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods.

F Nuclear Enthalpy Rise Hot Channel Factor, is defined as the y

ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

1 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper i

bound envelope times the normalized axial peaking fackorisnot l

exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The full length rods may be positioned within the core l

in accordance with their respective insertion limits and should be inserted near their normal position for steady state operation at high power levels.

The value of the target flux difference obtained under these conditions divided by the fraction.of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the

'j associated core burnup conditions.

Target flux differences for other i

THERMAL POWER levels are BEAVER VALLEY - UNIT 1 B 3/4 2-1

/ Wen &1ent No.16 }{. 744,154 I

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POWER DISTRIBUTION LIMITS 4

BASES obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level.

The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the target band about.the target flux l

difference, during rapid plant T7RMAL POWER reductions, control rod motion will cause the AFD to caviate outside of the target band at reduced THERMAL POWER L4vels.

This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited.

Accordingly, a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is provided for operation outside of the target band but within the limits specified in the CORE OPERATING LIMITS REPORT for THERMAL POWER levels between 50% and 90% of RATED THERMAL POWER.

For THERMAL POWER les41s between 15% and 50% of RATED THERMAL POWER, deviations of the i

AFD outside of the target band are less significant.

The penalty of i

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

j Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Honitor Alarm.

The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if i

the AFD for at least 2 of 4 or 2 of 3 OPERABLE excere channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER.

During operation at THERMAL POWER levels between 50%

and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

Figure B

3/4 2-1 shows a

typical monthly _ target band near the beginning of core life.

l i

i BEAVER VALLEY - UNIT I B 3/4 2-2

/Wendment No,'9, 744,154

(

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 AND 3/4.2.3 MEAT FLUX AND NUCLFAR ENTHALPY HOT CHANNEL FACTORS-F (Z) andFfg g

The limits on heat flux and nuclear enthalpy hot' channel factors ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the ECCS acceptance criteria limit of 2200*F.

Each of these hot channel factors are measurable but. will normally only be determined periodically

-as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to insure that the het channel factor limits are maintained provided:

a. Control-rods in a

single group move together with no individual rod insertion differing by more than 12 steps from the group demand position.

b. Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.

c. The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained,

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE is maintained within the limits.

N The relaxation in F

as a

function of THERMAL POWER allows 3

changes in tge radial power shape for all permissible rod insertion limits.

FaH will be maintained within its limits provided conditions a thru d above, are maintained.

When a

F measurement is

taken, both experimental error and q

manufacturing tolerance must be allowed for.

5% in the appropriate experimental error allowance for a

full core mop taken with the incore detector flux mapping system and 3%

is the appropriate allowance for manufacturing tolerance.

The specified

limit of F$

contains an 8t allowance for H

uncertainties which means gha

normal, full

power, three loop Fh. t operation will result in H

less than or equal to the design l

limit specified in the CORE OPEMTING LIMITS REPORT.

BEAVER VALLEY - UNIT 1 B 3/4 2-4 Amendment M0.13 744,154 3

i

1 POWER DISTRIBUTION LIMITS BASES Fuel rod bowing reduces the value of the DNB ratio.

Margin has been maintained between the DNBR value used in the aafety analyses (1.33) and the design limit (1.21) to offset the rod bow penalty and other penalties which may apply.

The radial peaking factor F

(Z) is measured periodically to provide assurance that the Hst chann.1

factor, r0 (z),

forRatedTherm81 Power (F[4ps reng

)

within its limit.

The F

limit provided in the CORE OPERNfING LIMITS REPORT was determined

[om l expected power control maneuvers over the full range of burnup conditions in the core.

3/4.2.4 OUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testing and periodically during power operation.

i The limit of 1.02 at which corrective action is required provides DNB l

and linear heat generation rate protection with x-y plane power j

tilts, j

i The two-hour time allowance for operation with

.a tilt condition i

greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod.

In the event such action does not correct the

tilt, the margin for i

uncertainty on r

is reinstated by reducing the maximum allowed g

power by 3 percent for each percent of tilt in excess of 1.0.

~

i BEAVER VALLEY - UNIT 1 B 3/4 2-5 Amendment No. W, W, H4, 154 I' ' l ' ' '

...is een

.g

.gi

ADMINISTRATIVE CONTROLS The radioactive effluent release report to be submitted 60 days after January 1

of each year shall also include an assesshent of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar-year to show conformance with 40 CFR

190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

The SKYSHINE code (available from Radiation Shielding Information Center, ORNL) is acceptable for calculating the dose contribution from direct radiation due to N-16.

The radioactive effluent release reports shall include an assessment-of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21.

In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.

The assessment of radiation doses shall be performed in accordance with the ODCM.

f The radioactive effluent release reports shall also include any l

licensee initiated changes to the ODCM made during the 6 month

[

period.

CORE OPERATING LIMITS REPORT 6.9.1.14 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a

reload cycle.

The analytical methods used to determine the core operating limits shall be thost

aviously reviewed and approved by the NRC in:

[

1.

WCAP-9272-P-A,

" WESTINGHOUSE RELOAD SAFETY EVAL 0ATION METHODOLOGY",

July 1985 (Westinghouse proprietary).

Methodology applied for the following Specifications:

i 3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control 3.2.2, Heat Flux Hot Channel Factor-FQ(Z) 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H 2.

WCAP-9220-P-A, Rev.

1,

" WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION",

February 1982 (Westinghouse Proprietary).

Methodology applied for the following Specification:

3.2.2, Heat Flux Hot Channel Factor-FQ(Z) 3.

WCAP-8385,

" POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT",

September 1974 (Westinghouse l

Proprietary).

Methodology applied for the following i

specification:

3.2.1, Axial Flux Difference-Constant Axial Offset Centrol BEAVER VALLEY - UNIT 1 6 - 2 *2 Amendment No. %, h%, TM, 154

1 i

l ADMINISTRATIVE CONTROLS 4.

T.

M.

Anderson to K.

Kniel (Chief of Core Performance Branch, NRC)

January 31, 1980

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package. Methodelogy applied for the following Specification:

3.2.1, Axial Flux Difference-Constant Axial Offset Control 5.

NUREG-0800, Standard Review

Plan, U.

S.

Nuclear Regulatory Commission, Section 4.3, Nuclear

Design, July 1981.

Branch Technical Position CPB 4.3-1, Westinghouse constant Axial Offset Control (CAOC),

Bev.

2, July 1981.

Methodology applied for the following Speci ficatior. :

3.2.1, Axial Flux Difference-Constant Axial Offset Control The 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.

The CORE OPERATING LIMITS

REPORT, including any mid-cycle revisions or supplements

thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.

S.

Nuclear Regulatory Commission, Document Control desk, within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

BEAVER VALLEY - UNIT 1 6-22a l

Anendment No.154

iS A80p fo,,

UNITED STATES g

NUCLEAR REGULATORY COMMISSION l

wAssiwoTow, c. c. posas

.s

%, *... +,/

DUQUESNE LIGHT COMPANY 4

OHIO EDISON COMPANY j

i THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY j

1 DOCKET N0. 50-412 BEAVER VALLEY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY CPERATING LICENSE i

Amendment ~No. 31 I

License No. NPF-73 1.

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

A.

The application for amendment by Duquesne Light Com>any, et al.

(the licensee) dated December 14, 1989 complies wit 1 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 1; B.

The facility will o)erate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized 1.

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 amendrent will not be inimical to the 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 satisfied.

l I-2.

Accordingly, 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. NPF-73 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications-contained-in Appendix A, as revised through Amendment No. 31, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendrent is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGU RY COMMISSION I

Jo

. Stolz, irector Project Directorate I-A i

Division of Reactor Projects - 1/II Office of Huclear Reactor Regula, tion

Attachment:

Changes to the Technical Specifications Date of Issuance:-

April 26,1990

l 1

ATTACHMENT Y9 LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE'NO. NPF-73 DOCKET NO. 50-412 9

' Replace the following pages of Appendix A (Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by amendment-number and contain vertical lines indicating the areas.of change.

~,

Remove Insert f

1-6 1-6 3/4 1-18 3/4 1-18 3/4 1-19 3/4 1-19 3/4 1-24 3/4 1-24 3/4 1-25 3/4 1-25 3/4 1-26 4

3/4.2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-4 3/4 2-5 3/4 2-4 3/4 2-6 3/4 2-5 3

3/4 2-7 3/4 2-6 3/4 2-8 3/4 2-9 3/4 2-7

{

3/4 2-10 3/4 2-8 3/4 2-11 3/4.2-9 3/4 2-12 3/4 2-10 3/4 2-13 3/4 2-11 3/4 2-14 3/4 2-12 i

B3/4 2-1 B3/4 2-1 B3/4 2-2 83/4 2-2 B3/4 2-4 B3/4.2-4 6-18 6-18 6-18a 1

o 1

i i

DUINITIONS VENTING 1.34 VENTING is the controlled process of discharging air or gas from a con-finement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air er gas is not provided or required during VENTING.

Vent, used in system names, does not. imply a VENTING process.

MAJOR CHANGES 1.35 MAJOR CHANGES to radioactive waste systems, as addressed in Para-graph 6.16.2, (liquid, gaseous and solid) shall include the.following:

1)

Major changes in process equipment, components, structures, and effluent monitoring instrumentation from those described in the Final Safety Analysis Report (FSAR) or the Hazards Summary Report and evaluated in the staff's Safety Evaluation Report (SER)

(e.g., celetion of evaporators and installation of domineralizers; usa of fluidized bed calciner/ incineration in place of cement solidification systems);

i 2)

Major changes in the design of radwaste treatment systems-(liquid, gaseous, and solid) that cobid significantly increase the quantities or activity of effluents released or volumes of solid waste stored or shipped offsite from those previously considered in the FSAR and SER (e.g., use of asphalt system in place of cement);

3)

Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released); and l

4)

Changes in system design that could potentially result in a significant j

increase in occupational exposure of operating personnel (e.g., use of l

temporary equipment without adequate shielding provisions).

(

MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the utility. its contractors, or its vendors.

Also excluded.from this category are l

persons who enter the site to service equipment or to make deliveries and persons who traverse portions of the site as the consequence of a public highway, railway, or waterway located within the confines of the site boundary.

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

CORE OPERATING LIMITS REPORT 1.37 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.14.

Plant operation within these operating limits is addressed in individual specifications.

BEAVER VALLEY - UNIT 2 1-6 Amendment No. 31

.m r

y.

,e-

,w*

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position, as determined in accordance j

with Specification 3.1.3.2) of their group step counter demand position.

APPLICABILITY:

MODES 1* and 2*

ACTION:

With one or more full length rods inoperable due to being immovable a.

as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of i

Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full length rod misaligned from.its group step counter demand position by more than i 12 steps (indicated position-determined in accordance with Specification 3.1.3.2), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , With one full length rod trippable but inoperable due.to causes other c.

than addressed by ACTION a above, or misaligned from its group step counter demand position by more than i 12 steps (indicated position determined in accordance with Specification 3.1.3.2), POWER OPERATION may continue provided that within one hour'either:

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 i 12 steps of the inoperable rod while maintaining the rod sequence and in-I sertion limits provided in the CORE OPERATING LIMITS REPORT.

l The THERMAL POWER level shall be restricted pursuant to Specifi-cation 3.1.3.6 during subsequent operation, or l

3.

The rod is declared inoperable and the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

i I

a)

The THERMAL POWER level is reduced to less than or equal i-to 75% of RATED THERMAL POWER within the hour and, within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

i

See Special Test Exceptions 3.10.2 and 3.10.3 L

l BEAVER VALLEY - UNIT 2 3/4 1-18 Amendment No,'17, 31

e l

i q

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)

A power distribution map is obtained from the movable incore detectors and F (Z) and Ffg.are verified to be q

within their ifmits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm i

that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

d.

With more than one rod trippable but inoperable due to causes other

(

than addressed by Action a above, POWER OPERATION may continue provided that:

1.

Within one hour, the remainder of the rods in the bank (s) with the inoperable rods are aligned to within *12 steps of the inoperable rods while maintaining the rod sequence and insertion limits provided in the CORE OPERATING LIMITS REPORT.

l 4

l The THERMAL POWER level shall be' restricted pursuant to Specifi-cation 3.1.3.6 during subsequent operation, and 2.

The inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

i J.

SURVEILLANCE REOUIREMENTS f

I I

4.1.3.1.1 Each shutdown and control rod not fully inserted in the core shall l

be determined to be OPERABLE by movement of at least 10 steps in any one i

direction at least once per 31 days.

4.1.3.1.2 The position of each full length rod shall be determined to be within L

i 12 steps of the associated group demand counter by verifying the individual rod position at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during intervals when the Rod i

i Position Deviation monitor is inoperable, then verify the group position at l

1 east once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l r

BEAVER VALLEY - UNIT 2 3/4 1-19 Amendment No.'17, 31

4 4

-w-a w

'4 s

j e

REACTIVITY CONTROL SYSTEM SHUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be within the insertion limits specified in the CORE OPERATING LIMITS REPORT.

i n

APPLICABILITY:

MODES 12 and 2*#

ACTION:

With a maximum of one shutdown rod inserted beyond the insertion limit, except for surveillance testing pursuant to Specification 4.1.3.1.1, within one hour either:

j a.

Restore the rod to within the limit, or l

]

b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

l

)

SURVEILLANCE REOUIREMENTS j

4.1.3.5 Each shutdown rod shall be determined to be within the insertion l'

limit:

Within 15 minutes prior to withdrawal of any rods in control banks A, a.

B, C, or D during an approach to reactor' criticality, and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

i 1

See Special Test Exception 3.10.2 and 3.10.3

With Keff > 1.0 BEAVER VALLEY - UNIT 2 3/4 1-24 Amendment No. 31

j REACTIVITY CONTROL SYSTEMS CONTROL ROD' INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be within the limits specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: MODES la and 2*#-

.A,CT1CH:

With the control banks inserted beyond the insertion limits, except for I

surveilience testing pursuant to Specification 4.1.3.1.1, either:

1 a.

Restore the control banks'to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

-i b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that-fraction of RATED THERMAL POWER which is allowed by the bank posi-tion insertion limits specified-in the CORE OPERATING LIMITS REPORT-l or c.

Be in at least HOT STANDBY wittin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits 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 rod insertion. limit monitor 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 .

i

See Special Test Exception 3.10.2 and 3.10.3

with Keff > 1.0 BEAVER VALLEY - UNIT 2 3/4 1-25 Amendment No. 31

3

,1 3/4.2-POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (AFD)

-l LIMITING CONDITION FOR OPERATION i

3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within i

the target band specified in the CORE OPERATING LIMITS REPORT (COLR).

APPLICABILITY:

MODE 1 above 50 Percent RATED THERMAL POWER

ACTION:

a.

With the indicated AXIAL FLUX DIFFERENCE outside of the target j-band and with THERMAL POWER:

i n

1.

Above 90 percent of RATED THERMAL POWER, within 15 minutes:

a)

Either restore the indicated AFD to within the target band I

limits, or b)

Reduce THERMAL POWER to less than 90 percent of RATED i

THERMAL ?OWER.

2.

Between 50 percent and 90 percent of' RATED THERMAL POWER:

a)

POWER OPERATION may continue provided:

1)

The indicated AFD has',not'been outside of the l

target band-for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation l

cumulative during the previcus 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and l

2)

The indicated AFD is within the target band.

Otherwise, l

reduce THERMAL POWER to'less than 50. percent of RATED' i

THERMAL POWER within 30 minutes and reduce-the Power Range Neutron Flux-High Trip Setpoints to < 55 percent.

of RATED' THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b)

Surveillance testing of the Power Range Neutron Flux Chan-nels may be performed pursuant to Specification 4.3.1.1~.'1 provided the indicated AFD is maintained within the limits.

i A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the target' band during this testing without penalty deviation.

l

See Special Test Exception 3.10.2 BEAVER VALLEY - UNIT 2 3/4 2-1 Amendment No. 31-p L-

a POWER DISTRIBUTION LIMITS

~1 LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) b.

THERMAL POWER shall not be-increased above 90 percent of RATED THERMAL POWER unless the indicated AFD is within the target band l

and ACTION a.2.a) 1), above has been satisfied.

t c.

THERMAL POWER shall not be increased above 50 percent of RATED t

THERMAL. POWER unless.the indicated AFD has not been outside of-I the target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation cumulative i

during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

L MRVEILLANCEREOUIREMENTS l

4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15. percent of RATED THERMAL POWER by:

4 a.

Monitoring the indicated'AFD for each OPERABLE excore channel-5 i

1.

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status.

D.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel-at least once per hour for the first

24. hours and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is. inoperable.

The logged values nf.the indicated AXIAL FLUX DIFFERENCE shall be assumed to exi.st during the interval preceding each logging.

4.2.1.2 The indicated AFD shall be considered outside of its target band when I

at leart~2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

POWER OPERATION outside of the target band shall l

i l:

be accumulated on a time basis of:

i t

One-minute penalty deviation for each 1 minute of POWER OPERATION a.

i outside of the target' band at THERMAL POWER 1evels equal to or above 50 percent of RATED THERMAL POWER, and i

b.

One-half-minute penalty deviation for each 1 minute of POWER t

OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

1 BEAVER VALLEY - UNIT 2 3/4 2-2 Amendment No.'2,, 31 j

POWER DISTRIBUTION LIMITS.

HEAT FLUX HOT CHANNEL FACTOR-F (Z) n l

4 LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) snell be limited by the following relationships:

q i

F (Z) < [CF0 ]-[K(Z)] for P,> 0.5 O

P F (Z) i [

] [K(Z)] for P $=0.5 9

Where: CFQ = The FQ iimit at RATED THERMAL POWER provided in the

{

CORE OPERATING LIMITS REPORT,.

4 K(Z) = Tiie. normalized F (2) as a function of core height 9

provided in the CORE OPERATING LIMITS REPORT, and p

THERMAL POWER

~ RATED THERMAL POWER-1, APPLICABILITY: MODE 1 i

i ACTION:

With F (Z) exceeding its limit:

9 j

Reduce THERMAL POWER at least 1 percent for each 1 percent F (2).

a.

q exceeds the limit within 15 minutes. and similarly reduce the: Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subse-quent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1 percent for-each 1-percent ij F (Z) exceeds the limit.

The Overpower AT Trip Setpoint reduction q

shall be performed with the reactor subcritical.

b.

Identify and correct the cause of the out'of limit condition prior to increasing THERMAL POWER: THERMAL POWER may then be increased provided F (2) is demonstrated through incore mapping to be within its limit q 1

\\

BEAVER VALLEY - UNIT 2 3/4 2-4 Amendment No. 31

.1 1

_,_q

,i

-POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F

-shall be evaluated to determine if F (Z) is within its limit by: *Y 9

i

-Using the movable incore detectors to obtain a power distribution a.

map at any. THERMAL POWER greater than 5 percent of RATED THERMAL

~,

POWER.

^

i, b.

Increasing the measured F component of the power distribution map xy by 3 percentJto account for manufacturing tolerances and further increasing the value by 5 percent to account for measurement

. uncertainties.

c.

Comparing the F computed (F

) btained in b, above to:

xy x

1.

The F limits for RATED THERMAL POWER (FRTP) for the xy x

appropriate measured core planes given in e and f below, and 2.

The relationship:

RTP F

=F

[1+PFXY(1-P)]

x x

where F is the limit for-fractional THERMAL POWER x

operation expressed as a function of F PFXY is the power factor multiplier for F provided in the CORE xy OPERATING LIMITS REPORT, and P is the fraction of RATED THERMAL POWER at which F was measured.

d.

Remeasuring F according to the following schedule:

xy RTP 1.

When F is greater than the F limit for the appropriate x

y measured core plane but less than the F l relationship, xy additional power-distribution maps shall be taken and F

compared to F and F x

x a)

Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20 percent of RATED THERMAL POWER or greater, the THERMAL POWER at which F was last determined, or b)

At least once per 31 EFPD, whichever occurs first.

BEAVER' VALLEY - UNIT 2 3/4 2-5 Amendment No. 31 1

J POWER DISTRIBUTION LIMITS f

SURVEILLANCE REOUIREMENTS (Continued) 2.

When the F

-is'less than or equal to the FRTP limit for the x

appropriate measured core plane,-additional power distribution C

l maps.shall be'taken and F*Y compared to F*RTP and'F*Y at least once per 31 EFPD.

Y-j e..

The F limit for Rated Thermal Power.(F

) shall be,provided for.-

xy x

all core planes containing-bank D" control rods and -all unrodded core planes in the~ CORE OPERATING' LIMITS REPORT.

I f.

The F limits of e, above, are not applicable in the following core xy plane regions as measured in percent of-core height from the bottom.

of the fuel:

1.

Lower core region from 0 to 15 percent,. inclusive.

2.

Upper core region from 85 to 100 percent inclusive.

4 I

3.

Grid plane regions of core height (1 2.88 inches) measured from grid centerline.

4.

Core plane regions-within i 2 percent of core h'eight (* 2.88 inches) about the bank' demand position of the bank "0" control rods.

g.

With F exceeding F

, the effects of F on F (Z) shall be xy xy 9

evaluated to determine if F (Z) is within-its limit..

9 4.2.2.3 When F (Z) is measured pursuant to Specification 4.10.2.2, an overall 9

measured F (Z) shall be obtained from a power distribution map-and increa!,ed by3perce9.ttoaccount'formanufacturingtolerancesandfurtherincreasedby 5 percent to account for measurement uncertainty.

i i

BEAVER VALLEY - UNIT 2 3/4 2-6 Amendment No. 31 l

pro

. = - -

-=a e

POWER DISTRIBUTION LIMITS NUCLEARENTHALPYHOTCHANNELFACTOR-FfH I

1-QMITINGCONDITIONFOROPERATION (Hshallbelimitedbythefollowingrelationship:

3.2.3 i

Fh5CFDH[1_+PFDH(1-P)]

!-i CFDH=TheFfg limit at RATED THERMAL POWER provided in the where:

CORE OPERATING' LIMITS REPORT, N

PFDH = The Power Factor multiplier for F CORE' OPERATING LIMITS REPORT, ana#H provided_in the I

l THERMAL POWER P = RTIED THERMAL POWER l

APPLICABILITY: MODE 1 L

ACTION:

With F exceeding its limit:

H Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within a.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to i 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Demonstratethroughin-coremappingthatFhiswithinitslimit b.

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit'or reduce THERMAL POWER to less than 5 percent of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and Identify and correct the cause of the out of limit condition prior c.

-to increasing THERMAL POWER, subsequent POWER OPERATION may proceed provided that F is demonstrated through-ic-coro manning to be g

within its limit at a nominal 50 percent af RATtD iHERMAL POWER prior to exceeding this THERMAL power, tt a> nominal 75 percent of RATED THERMAL POWER prior to exceeding this THCRMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95 percent or greater RATED THERMAL POWER.

BEAVER VALLEY - UNIT 2 3/4 2-7 Amendment No. 31 l

l

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.3.1 F

shall be determined to be within its limit by using movable.

~

H incore detectors to obtain a power distribution map:

Prior to operation above 75 percent of RATED THERMAL POWER after a.

each fuel loading, and j

b.

At~le:.t once per 31 Effective Full Power Days.--

ThemeasuredFfg of 4.2.3.1 above, shall be increased by 4% for 4.2.3.2 measurement uncertainty.

'I 4

J i

I l

BEAVER VALLEY - UNIT 2 3/4 2-8 Amendment No. 31 l

l

POWER-DISTRIBUTION LIMITS

-QUADRANT POWER TILT RATIO 1

l LIMITING CONDITION FOR OPERATION 3.2.4 THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

l APPLICABILITY:

MODE.1 above 50 Percent OF RATED-THERMAL POWER

o

)

ACTION:

\\

With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but a.

1 1.09:

1 1.

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

j a)

Either reduce the QUADRANT POWER TILT RATIO to within l

{

its limit, or

[

b)

Reduce THERMAL' POWER at least-3 percent for-each 1 percent

i L

of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High l'

Trip Setpoints within the next-4 hourc.

l 2.

Verify that the QUADRANT POWER TILT RATIO'is within its limit.

{

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceedingtthe limit or reduce THERMAL POWER to less than 50 percent o' RATED THERMAL-POWER within the i

next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip setpoints to 5 55% of RATED THERMAL POWER within-the next-4 hours.

3.

Identify and correct the cause of:the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50 percent of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within~its limit at least once per hour until verified acceptable at 95% or greater RATED THERMAL POWER.

b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1.

Reduce THERMAL POWER at least 3 percent for each 1 pertant of indicated QUADRANT POWER TILT RATIO in excess of 1.0, within 30 minutes.

2.

Verify that the QUADRANT POWER TILT-RATIO is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months af ter exceeding the limit or reduce THERMAL POWER to less than 50 percent of RATED THERMAL POWER within the next-2 hours and reduce the, Power Range Neutron Flux-High Trip Set-points ~to 1 55 percent of RATED THERMAL POWER within the next 4

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exception 3.10.2 BEAVER VALLEY - UNIT 2 3/4 2-9 Amendment No. 31 l

~

=

P

~ POWER' DISTRIBUTION LIMITS

,e LIMITING CONDITION FOR OPERATION (Continued) i 3.

' Identify and correct the cause.of the out of limit condition t

prior to increasing THERMAL P0WER; subsequent POWER OPERATION.

i:

above 50. percent of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT. RATIO is verified within its i

. limit atLleast once per hour until verified acceptable at 95%

~

or greater RATED THERMAL POWER.

c.

-With the QUADRANT POWER TILT. RATIO determined to exceed 1.09 due to causes other than the misalignment-of either a shutdown or control rod.-

7 1.

Reduce THERMAL POWER to less than 50%'of RATED THERMAL. POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip-Setpoints to s 55% of kAiED THERMAL-POWER within the r

next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

t i

2.

Identify and correct the cause of the.out of limit-condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50 percent of RATED THERMAL POWER.may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour until verified at 95% or greater RATED THERMAL POWER.

SURVEILLANCE REOUIREMENTS t

4.2.4 The QUADRANT POWER TILT RATIO chall be determined to be within the limit j

above 50% of RATED THERMAL POWER by:

i a.

Calculating the ratio at least once per 7 days when the alarm is OPERABLE.

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state operation when the alarm is inoperable.

Using the movable detectors to determine the QUADRANT POWER TILT c.

RATIO.at'least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when one Power Range Channel is inoperable and THERMAL POWER is > 75 percent of RATED THERMAL POWER.

i..

l l

i-l l

[

BEAVER VALLEY - UNIT 2 3/4 2-10 Amendment No. 31 l

~

t w-w w

w vv iwNe si er

POWER DISTRIBUTION LIMITS-DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on-Table 3.2-1:

-Reactor Coolant System T,yg a.

b. -

Pressurizer Pressure c.

Reactor Coolant System-Total Flow Rate APPLICABILITY:

MODE 1*

i ACTION:

I With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than i

5 percent of RATED THERMAL-POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , i

SURVEILLANCE REOUIREMENTS 4.2.5.1.1 Each of the parameters of Table 3.2-1 shall be verified to be indi-cating within their limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.1.2 The provisions of Specification 4.0.3 and 4.0.4 are not applicable for the reactor startups following the initial fueling for Reactor Coolant I

System total flow rate to allow a calorimetric flow measurement-and the cali-bration of the Reactor Coolant System total flow rate indicators, l

4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its. limit by measurement at least once per 18 months, i

The provisions of Specification 3.0.2 are not applicable for the reactor startup following the initial fueling for Reactor Coolant System total flow rate to allow a calorimetric flow measurement and the calibration of the j

Reactor Coolant System total flow rate indicators.

BEAVER VALLEY - UNIT 2 3/4 2-11 Amendment No. 31 l

I i.'

4 TABLE'3.2-l' DNB-PARAMETERS-i 1

I 3 Loops-in.

t PARAMETER Operation

' Reactor. Coolant System T,yg

< 580.2*F

. Pressurizer Pressure 1 2220 psia *

]

Reactor Coolant System 1 274,800 gpm**

i Total Flow Rate n

.I

- 1 I

i I

Limit not' applicable during either a THERMAL POWER ramp increase in excess of 5 percent RATED THERMAL POWER per minute or a THERMAL POWER step increase in-excess of 10% RATED THERMAL POWER.

- Includes a 3.5% flow measurement uncertainty.

BEAVER VALLEY - UNIT 2 3/4 2-12 Amendment No. 31 l

{

W f!

J, N

i f

3/4.2 POWER DISTRIBUTION LIMITS l

7 1

BASES I

The specifications of this section provide assuranceof fuel integrity i

during Condition I (Normal Operation) and II (Incidents of Moderate Frequency)-

events by:

(a) maintaining the minimum DNBR in the core > 1.30 during normal operation and in short term transients, and (b) limiting the. fission gas. release,

{

I fuel pellet temperature and cladding mechanical properties to within assumed de-sign criteria.

In addition, limiting the peak linear power density during Con-dition I events provides assurance that the initial conditions assumed for the

{

LOCA~ analyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.

The definitions of hot channel factors as used in these specifications are as follows:

F (Z)

Heat Flux Hot Channel Factor, is def % d as-the maximum local heat q

flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances.on

-i fuel pellets and rods.

F g Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

e 3/4.2.1 AX1AL FLUX DIFFERENCE (AFO)

The limits on AXIAL FLUX DIFFERENCE assure that the F (Z)_ upper bound-9 envelope times the normalized axial peaking factor is not exceeded during l

either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady state operation at high power levels. -The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions.

Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level.

The periodic updating of the target-flux difference value is necessary to reflect core burnup considerations.

Although it is intended that the plant will be operated.with the AXIAL FLUX DIFFEREtlCE within the target band about the target flux difference, I

during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels.

]

This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time 1

1 BEAVER VALLEY - UNIT 2 B 3/4 2-1 Amendment No. 31

- c-6 POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (AFD) (Continued)

-l duration limit of the deviation is limited..Accordingly, a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty de-viation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is provided for operation outside of the target band but within the limits specified in the CORE OPERATING LIMITS REPORT for THERMAL POWER levels between 50% and 90% of RATED j

THERMAL POWER.. For THERMAL POWER levels between 15%:and 50% of RATED THERMAL-i POWER, deviations of the'AFD outside of the target band are less-significant.

l The penalty of 2' hours actual time reflects this reduced significance.

1';

. Provisions for monitoring the AFD on an automatic' basis are derived from

-l the plant process computer through the AFD Monitor Alarm.

The-comouter deter-mines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2.

of 3 OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of' RATED THERMAL-POWER.

During operation at THERMAL' POWER levels between 50% and 90% and between 15% and 50% of RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond t

.the limits of 1~ hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,'respectively. '

Figure B 3/4 2-1 shows a typical monthly target band near the beginning of--

core life.

1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS i

F (Z)and FN n

AH The limits on heat flux and nuclear enthalpy. hot -channel factors ensure-that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will'not exceed the ECCS acceptance critoria limit of 2200*F.

Each of these hot channel factors are measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:

Control rods in a single group move together-with no individual rod a.

insertion differing by more than i 12 steps from the group demand position.

b.

Control rod groups are sequenced'with overlapping groups as-described in Speci fication 3.1. 3.6.

BEAVER VALLEY - UNIT 2 B 3/4 2-2 Amendment No. 31

n C

l POWER DISTRIBUTION LIMITS i

BASES 1

^

3/4.2.2 and 3/4 2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS F (Z) n AND F H (Continued) c.

The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.

d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE'is maintained within the limits.

j The relaxation in FfH as a function of THERMAL POWER allows changes in the radial power shape for all-permissible rod insertion limits.

F will be AH maintained within its limits provided conditions.a thru d above, are maintained.

When an F measurement is taken, both experimental error and manufacturing i

g tolerance must be allowed for.

5% is the appropriate experimental error allow-ance for a full core map taken with the.incore detector flux mapping system and 3% is the appropri. ate allowance for manufacturing tolerance.

j The sw !fied limit of F contains an 8% allowance for uncertainties which H

means that c.ormal, full power, three loop operation will result in F H 1 less j

than or equal to the design limit specified in the CORE OPERATING LIMITS REPORT.

Fuel rod bowing reduces the value of the DNB ratio.

Credit is available to offset this reduction in the generic margin.

The generic design margins, I

totaling 9.1% DNBR, and completely offsets any rod bow penalties (< 1.3% for the i

worst case which occurs at a burnup of 24,000 MWD /MTU).

4 This margin includes the following:

1.

Design Limit DNBR of 1.30 vs. 1.28 2.

Grid Spacing (K ) f 0.046 vs. 0.059 s

3.

Thermal Diffusion Coefficient of 0.038 vs. 0.059 4.

DNBR Multiplier of 0.865 vs. 0.88 5.

Pitch reduction i

The radial peaking factor Fxy (Z) is measured periodically to provide assurance that the hot channel factor, F RTP)q (Z), remains within its limit. The F

limit for Rated Thermal Power (F provided in the CORE OPERATING xy x

LIMITS REPORT was determined from expected power control maneuvers over the full range of burnup conditions in the core.

3/4.2.4 QUADRANT POWER TILT RATIO The Quadrant Power Tilt Ratio limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis.

i BEAVER VALLEY - UNIT 2 B 3/4 2-4 Amendment No. K 31

l ADMINISTRATIVE CONTROLS SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

{

The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

The SKYSHINE Code (availcble from Radiation Shielding i

Information Center, (ORNL) is acceptable for calculating the dose contribution from direct radiation due to N-16.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from i

the unit during each calendar quarter as outlined in Regulatory Guide 1.21.

In adc'.ition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.

The assessment of radiation doses shall be per-formed in accordance.with ODCM.

The radioactive effluent release reports shall also include any licensee 4

initiated changes to the ODCM made during the 6 month period, i

CORE OPERATING LIMITS REPORT 6.9.1.14 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1.

WCAP-9272-P-A. "WESTINGH0'SE RELOAD SAFETY EVALUATION METHODOLOGY", July u

1985 (Westinghouse Proprietary).

Methodology applied for the following Specifications:

3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control 3.2.2, Heat Flux Hot Channel Factor-F (Z) q 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H 2.

WCAP-9220-P-A, Rev.1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION",

February 1982 (Westinghouse proprietary).

Methodology applied for the following Specification:

3.2.2, Heat Flux Hot Channel Factor-F (Z) q 3.

WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOPICAL REPORT", September 1974 (Westinghouse Proprietary).

Methodology applied for the following Specification; 3.2.1, Axial Flux Difference-Constant Axial Offset Control.

4.

T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC)

January 31, 1980 --

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

Methodology applied for the following

'1 Specification:

3.2.1, Axial Flux Difference-Constant Axial Offset Control.

BEAVER VALLEY - UNIT 2 6-18 Amendment No. b, 31 l

]

i ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 5.

NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, I

Section 4.3, Nuclear Design, July 1981.

Branch Technical Position CPB y

4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981. Methodology applied for the following Specification:

3.2.1, Axial l

Flux Difference-Constant Axial Offset Control The core operating limits shall be. determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS i

limits, nuclear limits such as shutdown margin, and transient and accident analysis limits)'of the safety analysis are met.

The CORE OPERATING LIMITS i

REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk.

SPECIAL REPORTS I

6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk within the time period specified for each j

report. These reports shall be submitted covering the activities-identified below pursuant to the requirements of the applicable reference specification:

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

a.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation, c.

Specification 3.3.3.4.

i h

BEAVER VALLEY - UNIT 2 6-18a Amendment No. M, 31 1

ML20042F061

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