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Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by
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Site:	Beaver Valley
Issue date:	07/15/1999
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ATTACHMENT 262 Unit No. 1 Technical 3Decification Paces 1

j i

RA7"iEIA E'YJ*

J P

(_

~

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-65

' DOCKET NO. 50-334 i

Replace the following pages ofIAppendix 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 3/4'l-19 3/4 1-19 3/4 1-20 3/4 1-20 3/4 1-20b 3/4 1-20b 3/4 1-20c 3/4 1-20c 3/4 1-23 3/4 1-23 3/4'1-23a 3/4 1-23a 3/4 2-2 3/4 2-2 3/4 2-11 3/4 2-11 B 3/4 1-4 B 3/4 1-4 B 3/4 2-7 B 3/4 2-7 B 3/4 2-10 B 3/4 2-10 1

5 DPR l MITkNGCONDITIONFOROPERATION'(Continued)

I 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 wit {Un

-movable incore detectors and FQ(Z) and F

are verified to be within their limits h

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

d.-

With more than one rod tripable but inoperable due to causes other than addressed by Action a

above, POWER OPERATION may continue provided that:

l 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.

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 .

I SURVEILLANCE REQUIREMENTS 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 once per 31 days.

4.1.3.1.2 Tne position of each full length rod shall be determined to be within-12 steps of the associated group demand counter by j

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 .

l l

l

See Special Test Exception 3.10.2 and 3.10.4 BEAVER VALLEY - UNIT 1 3/4 1-19 Amendment No.

1 DPR-66 l

REACTIVITY CONTROL SYSTEMS

.EQJITbON INDICATION SYSTEMS-OPERATING l

(

LIMITING CONDITION FOR OPERATION j

3.1.3.2 The shutdown,.d control rod position indication system shall be OPERABLE as follows:

il)

Group Demand Counter 1 per group Individual analog rod instrument channel, 1 per rod 112 steps (1) accuracy (3) position I

1 (1)

During the first hour following rod motion, the group demand counter is the primary indicator of precise rod position information, with the analog channels displaying general rod i

movement information.

For power levels below 50%,

a 1-hour thermal soak time is allowed. before the analog channels are required to perform within the specified accuracy.

(2)

For power levels below - 50% a one hour thermal soak time is allowed.

l (3)

Malfunctions of the group demand counters or analog

RPI, providing no actual rod misalignment existed during the malfunction, shall be reported in the monthly operating report.

BEAVER VALLEY - UNIT 1 3/4 1-20 Amendment No.

t.

1 DPR-66 l

^

LIMITING CONDITION FOR OPERATION (Continued) l e.

If the position-of a maximum of one rod cannot be determined by either the direct reading ' of the rod position indicators or by reading primary detector voltage measurements, 1.

Determine the position of the non-indicating rod indirectly.by the movable incore detectors immediately and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position.

f.

If the position of more than one rod cannot be determined by either the direct reading of the rod position indicators or by reading primary detector voltage measurements, then Specification 3.0.3 is applicable.

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL power within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

I SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each of the group demand counters shall be determined to

.be OPERABLE by:

a.

Performing a CHANNEL CHECK by the group demand counters within a

bank, and observing proper overlap

of the indicated positions, and b.

Performing a CHANNEL CHECK by an intercomparison between the control bank benchboard indicators and the logic solid state indicators in the logic cabinet, and determining their agreement within i2

steps, at least once per 92 days.

During startup and shutdown, overlap must be checked for all control banks at the respective bank overlap height transition points.

BEAVER VALLEY - UNIT 1 3/4 1-20b Amendment No.

l DPR-66 l

SURVE[LLANCE REQUIREMENTS (Continued) 4.1.3.2.2 Each of the analog rod position indicators shall be determined to be OPERABLE by:

a.

Performing a CHANNEL CHECK by intercomparison** between each analog rod position indicator and its corresponding group demand-counter at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

Performing a

CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at least once per its months.

For Core PHYSICS TESTING in Mode 2,

primary detector voltage measurements may be used to determine the position of rods in shutdown banks A and B and control banks A and B for the purpose of satisfying Specification 3.1.3.2.

During Mode 2 operation, rod position indicators for shutdown banks A and B and control banks A and B may deviate from the group demand indicators by j

greater ti sn

' 12 steps during reactor startup and shutdown operations, while rods are being withdrawn or inserted.

If the rod position indicators for shutdown banks A and B and control banks A and B deviate by greater than 12 steps from the group demand indicator, rod withdrawal or insertion'may continue until the desired group height is achieved.

When the desired group height is achieved, a one hour soak time is allowed below 50%

reactor power to permit stabilization of the rod position analog l

indicators.

.To attain thermal equilibrium during the one hour soak time, the absolute value of rod motion shall rs at exceed 6 steps.

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.

' BEAVER VALLEY - UNIT 1 3/4 1-20c Amendment No.

~

DpR-66 l

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.

APPLICABILITY: MODES 1* and 2*/

ACTION:

l 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:

a.

Restore the rod to within the limit, or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit **:

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

l

)

1 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 2 1.0.

l i

BEAVER VALLEY - UNIT 1 3/4 1-23 Amendment No.

y DPR-66 l

-REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION l

3.1.3.6 The control banks shall be within the insertion limits i

specified in the CORE OPERATING LIMITS REPORT.

1 APPLICABILITY:

Modes 1* and 2*#

ACTION:

With'the control banks inserted beyond the insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.1, either:

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 that fraction or RATED THERMAL POWER which is allowed by the bank position insertion limits specified in the CORE OPERATING 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 .

SURVEILLANCE REQUIREMENTS 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 .

See Special Test Exception 3.10.2 and 3.10.4

.. With K.gf 2 1.0 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.

BEAVER VALLEY - UNIT 1 3/4 1-23a Amendment No.

I

DPR-66 l

POWER DISTRIBUTION LIMITS

-LIMITING CONDITION FOR OPERATION (Continued) b.

THERMAL-POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the target band and ACTION a.2.a) 1), above has been satisfied.

c.

THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of 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 during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 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 for each OPERABLE excore channel at least once per 7 days.

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

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

i 4

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

DPR-66 POWER DISTRIBUTION LIMITS l

SURVEILLANCE REQUIREMENTS

)

4.2.4 Verify the QPTR is within the limit:

'By calculation (2) at least once per 7 days.

a.

b.

Using the movable incore detectors once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12. hours thereafter.(3) l l

(2)

With one power range high neutron flux channel input to QPTR inoperable and, THERMAL POWER less than 75 percent RTP, the remaining three power range high neutron flux channels can be used for calculating the QPTR.

(3)

Only required to be performed with less than four power range high neutron flux channels input to QPTR operable with THERMAL POWER greater than or equal to 75 percent RTP.

BEAVER VALLEY - UNIT 1 3/4 2-11 Amendment No.

DPR-66

+

l REACTIVITY CONTROL SYSTEMS BASES position indicators (after thermal soak after rod motion) is sufficient verification that the control rods are above the insertion limits below 50 percent power.

Above 50 percent power, reliance is placed on the analog rod position indicator channels to assure that control rods are above the insertion limits.

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

Misalignment of a rod requires measurement of. peaking factors and a restriction in THERMAL POWER.-

These restrictions provide assurance of fuel rod integrity

-during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

For Specification 3.1.3.1 ACTION c. and d.,

it is incumbent upon the plant to verify the trippability of the inoperable control rod (s).

Trippability is defined in Attachment C

to a

letter dated December 21, 1984, from E.

P.

Rahe (Westinghouse) to C.

O.

Thomas

(NRC).

This may be by verification of a control system failure, usually electrical in nature, or that the failure is associated with the control rod stepping mechanism.

In the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under'the requirements of ACTION a.

l I

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

l DPR-66 POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO (OPTR) (Continued)

L.Q_Q The QPTR limit of 1.02, at which corrective action is required, j

provides a margin of protection for both the DND ratio and linear j

l heat generation rate contributing to excessive power peaks resulting from X-Y plane power tilts.

A limiting QPTR of 1.02 gan be tolerated before the margin for uncertainty in Fg(Z) and (Fan) is possibly challenged.

l APPLICABILITY The OPTR limit must be maintained in MODE 1 with THERMAL POWER greater than 50 percent RATED THERMAL POWER (RTP) to prevent core power distributions from exceeding the design limits.

l l

Applicability in MODE 1 less than or equal to 50 percent RTP and in other MODES is not required because there is either insufficient stored energy in the fuel or insufficient energy being transferred to the reactor coolant to require the implementation of a QPTR limit on the distribution of core power.

The QPTR limit.ip these conditions is, therefore, not important.

Note that the F AH and Fg(Z) LCOs still

apply, but allow progressively higher peaking factors at l

50 percent RTP or lower.

ACTION a.

With the QPTR exceeding its limit, a power level reduction of 3 percent RTP for each 1 percent by which the QPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power.

The completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months allows sufficient time to identify the cause and correct i

the tilt.

rate that the power reduction itself may cause a change in the tilted condition.

h.

After completion of ACTION a, any additiornal changes in the l

QPTR are detected by requiring a check of the QPTR once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

If the QPTR continues to increase, THERMAL POWER has to be reduced accordingly.

A 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months completion time is sufficient because any additional change in QPTR would be relatively slow.

l l

BEAVER VALLEY - UNIT 1 B 3/4 2-7 Amendment No.

l

DPR-66 POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO (OPTB) (Continued)

' SURVEILLANCE REOUIREMENTS (SR)

SR 4.2.4.a SR 4.2.4.a is modified by a Note that allows QPTR to be calculated with three power range high neutron flux channels that input to QPTR if THERMAL POWER is less than 75 percent RTP and one power range high neutron flux channel is inoperable.

This surveillance verifies that the QPTR, as indicated by the Nuclear Instrumentation System (NIS) channels, excore channels, is within its limits.

The frequency of 7 days takes into account other information j

and alarms available to the operator in the control room.

I 1

For those causes of QPT that occur quickly (e.g.,

a dropped rod),

l there typically are other indications of abnormality that prcmpt a verification of core power tilt.

SR 4.2.4.b This surveillance is modified by a Note, which states that it is required only when less than four power range high neutron flux channels input to QPTR are operable and the THERMAL POWER is greater than or equal to 75 percent RTP.

With an excore detector inoperable, tilt monitoring for a portion of the reactor core becomes degraded.

Large tilts are likely detected with the remaining channels, but the capability for detection of small power tilts in some quadrants is decreased.

Performing SR 4.2.4.b at a frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months provides an accurate alternative means for ensuring that any tilt remains within its limits.

For purposes of monitoring the QPTR when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the indicated QPTR and any previous data indicating a tilt.

The incore detector monitoring is performed with a full incore flux map or a partial-core flux map with quarter core symmetry detailed in accordance with controlled procedures.

BEAVER VALLEY - UNIT 1 B 3/4 2-10 Amendment No.

\\

ATTACHMENT 135 Unit No. 2 Technical specification Paces i

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 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.

J Remove Insert 1

3/4 1-19 3/4 1-19 3/4 1-21 3/4 1-21 3/4 1-24 3/4 1-24 3/4 1-25 3/4 1-25 3/4 2-2 3/4 2-2 3/4 2-10 3/4 2-10 B 3/4 1-5 B 3/4 1-5 B 3/4 2-7 B 3/4 2-7 B 3/4 2-9 B 3/4 2-9 B 3/4 2-10 B 3/4 2-10

~

NPF-73 l

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

The SHDZUOWN 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 Fg(Z) and F$g are l

verified to be within their limits within l

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 that the previously I

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 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 .

SURVEILLANCE REQUIREMENTS 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 once per 31 days.

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

l BEAVER VALLEY - UNIT 2 3/4 1-19 Amendment No.

1 NPF-73 l

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod. Position Indication System and the Demand Position Indication' System shall be OPERABLE and capable of determining the control rod positions within i 12 steps.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With a maximum of one digital rod position indicator per bank inoperable either:

1.

Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and'immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , b.

With a maximum of one demand position indicator per bank inoperable either:

1.

Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum 12 ateps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital-Rod Position Indication System agree within 12 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l BEAVER VALLEY - UNIT 2 3/4 1-21 Amendment No.

l v.

NPF-73 l

REACTIVITY CONTROL SYSTEM SMUTDdWN 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.

APPLICABILITY:

MODES 1* and 2*#

ACTION:

l i

l 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:-

a.

Restore the rod to within the limit, or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

j SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit:

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 j

b.

_At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

l

See Special Test Exception 3.10.2 and 3.10.3

With K gf 2 1.0 BEAVER VALLEY - UNIT 2-3/4 1-24 Amendment No.

\\

NPF-73 l

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 1* and 2*/

ACTION:

With the control banks inserted beyond the insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.1, either:

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 that fraction of RATED THERMAL POWER which is allowed by the bank position insertion limits specified in the CORE OPERATING 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 .

SURVEILLANCE REQUIREMENTS 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 .

l

See Special Test Exception 3.10.2 and 3.10.3

With K rg 2 1.0 BEAVER VALLEY - UNIT 2 3/4 1-25 Amendment No.

^

NPF-73 l

POWER DISTRIBUTION LIMITS LIMITINGCONDIT}ONFOROPERATION (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 and ACTION a.2.a)1), above has been satisfied.

c.

THERMAL POWER _shall not be increased above 50 percent of RATED THERMAL POWER unless the indicated AFD has not been outside ' of. 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 during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

)

SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION abt/e 15 percent of RATED l

THERMAL POWER for each OPERABLE excore channel at least once per i

i 7 days.

4.2.1.2 The indicated AFO shall be considered outside of its target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are j

indicating the AFD to be outside the target band.

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

a.

One-minuto penalty deviation for each 1 minute of POWER OPERATION outside of-the target band at THERMAL POWER levels equal to or above 50 percent of RATED. THERMAL POWER, and b.

One-half-minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

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

~

NPF-73 POWER' DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4 Verify the QPTR is within the limit:

By calculation (2) at least once per 7 days.

a.

b.

Using the movable incore detectors once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.(3)

)

i 4

(2) -With one power range high neutron flux channel input to QPTR inoperable and THERMAL POWER less than 75 percent RTP, the

' remaining three power range high neutron flux channels can be used for calculating the QPTR.

(3)

Only required to _be performed with less than four power range high neutron flux channels input to QPTR operable with THERMAL POWER greater than or equal to 75 percent RTP.

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

.NPF REACTIVITY CONTROL' SYSTEMS BASES 3/4.1.2 BORATION SYSTEMS (Continued) satisfied before the verification is completed to easure that no unacceptable reduction.'of SHUTDOWN MARGIN occurred when the LCO requirements were not satisfied.

The primary function of. the surveillance is to ensure that the valve (s) used to isolate the Primary Grade Water System are locked, sealed or otherwise secured.

The frequency of 31 days to ensure.that the Primary Grade Water System fis properly isolated is bar:3 on engineering judgment, and has proven to be acceptable.

Opet7cing experience has shown that the failure rate is so low that the 31 day frequency is. justified.

A time frame of 15 minutes provides a minimum reasonable time for an operator to isolate the Primary Grade Water System following a planned activity requiring its use.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications' of this section ensure that 1) acceptable power distribution limits are maintained, 2) the minimum SHUTDOWN MARGIN is maintained,. and 3) the potential effects of rod misalignment on associated accident analyses are limited.

OPERABILITY of the movable control assemblies is established by observing rod motion and determining that rods are positioned within i 12 steps (indicated position), of the respective group demand. counter position.

The 1

OPERABILITY of the control rod position indication system is required to. determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

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

Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER.-

These - restrictions provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain. valid during future operation.

The maximum rod' drop time restriction is consistent with the assumed rod drop time used in the safety analyses.

Measurement with Tavg greater than or equal to 541 F and with all reactor coolant BEAVER VALLEY

. UNIT 2 B 3/4 1-5 Amendment No.

L NPF-73 l

POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO (OPTR)(Continued)

APPLICABILITY (Continued) the reactor coolant to require the implementation of a QPTR limit on the distribution'of core power.

The QPTR limit g these conditions is, therefore, not important.

Note that the F AH and Fg(Z) LCOs still apply, but allow. progressively higher peaking factors at 50 percent RTP or lower.

ACTION A.

With the QPTR exceeding its limit, a power level reduction of 3" percent RTP for. each 1 percent by which the QPTR exceeds 1.00 is a conservative tradeoff of-total core power with peak linear power.

The completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months allows. suf ficient time to identify the cause and correct the tilt.

Note that the power reduction itself may cause a change in the tilted condition,

b. -

After completion of ACTION a, any additional changes in the l

QPTR are detected by requiring.a check of the QPTR once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

If the QPTR continues to increase,

-THERMAL POWER has to ' be reduced accordingly.

A 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months completion time is sufficient because any additional change in QPTR would be relatively slow.

J i

s.

The. peaking factors F"An and Fg(Z) are of primary j

.importance in. ensuring that the power distribution remains consistent with the _ initial conditions used,in the safety analyses.

Perfor:aing surveillances on F AH and Fg(Z) within the completion time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensures that these i

primary indicators _ of power distribution are within their respective limits.

A completion time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months takes into consideration the rate at which peaking factors are likely to. change, and the time required to stabilize the 4

plant and. perform a flux map.

If these peaking factors are not within their limits, the actions provide an appropriate response for the abnormal condition.

If the QPTR remains j

-above its specified limit, thepeaking.factorsurveiglances are required = each 7 days ' thereaf ter to evaluate F AH and Fg(Z) with changes in power distribution.

Relatively small changes -are expected due to either burnup and xenon redistribution or correction of the cause for exceeding the QPTR limit.

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

NPF-73 POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO (OPTR)(Continued)

ACTION (Continued) power does not reach RTP within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but is increased

slowly, then the peaking factor surveillances must be performed within - 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the time when the ascent to power was' begun.

These completion times are intended to allow adequate time to increase THERMAL POWER to above the limit of ACTION a or b, while not permitting the core to remain with unconfirmed power distributions for extended periods of~ time.

This action assures that the peaking factor surveillances may only be done after the excore detectors have been normalized to show a tilt less than or equal to 1.02 (i.e.,

ACTION e)..

The intent of this is to have the peaking factor surveillances performed at operating power levels, which can only be accomplished after the excore detectors are normalized to show a tilt less than or equal to 1.02 and the core returned to power.

g.

If ACTIONS a through f are not completed within their associate 1 completion times, the unit must be brought to a MODE or condition in which the requirements do not apply.

To achieve this status, THERMAL POWER must be reduced to less than 50 percent RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The allowed completion time of 4

hours is reasonable, based on operating experience regarding the amount of time required to reach the reduced power level without challenging plant systems.

SURVEILLANCE REOUIREMENTS (SR) j i

I

'SR 4.2.4.a SR; 4.2.4.a is modified by a Note that allows QPTR to be calculated with three power range high neutron flux channels that input to QPTR if THERMAL POWER is less than 75 percent RTP and one power range high neutron flux channel is inoperable.

This surveillance verifies that the QPTR, as indicated by the Nuclear Instrumentation System (NIS) channels, excore channels, is within its limits._ The frequency of 7 days takes into account other information and alarms available to the operator in the control room.

-BEAVER VALLEY - UNIT 2 B 3/4 2-9 Amendment No.

NPF-73 POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO (OPTR) (Continued)

SURVEILLANCE REOUIREMENTS (SR) (Continued)

For those causes of QPT that occur quickly (e.g.,

a dropped rod),

l there typically are other indications of abnormality that prompt a verification of core power tilt.

)

SR 4.2.4.b I

This surveillance is modified by a Note, which states that it is i

required only when less than four power range high neutron flux channels input to QPTR are operable and the THERMAL POWER is greater than or equal to 75 percent RTP.

With an excore detector inoperable, tilt monitoring for a portion of the reactor core becomes degraded.

Large tilts are likely detected with the remaining channels, but the capability for detection of small power tilts in some quadrants is decreased.

Performing SR 4.2.4.b at a frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months provides an accurate alternative means for ensuring that any tilt remains within its limits.

For purposes of monitoring the QPTR when one excore detector is 1

inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the indicated QPTR and any previous data indicating a tilt.

The incore detector monitoring is performed with a full incore flux map or a partial core flux map with quarter core symmetry detailed in accordance with controlled procedures.

The symmetric thimble flux map can be used to generate symmetric thimble " tilt."

This can be compared to a reference symmetric thimble tilt, from the most recent full core flux cap, to generate an incore QPTR.

Therefore, the symmetric thimble flux map can be used to confirm that QPTR is within limits.

With one excore detector inoperable, the indicated tilt may be changed from the value indicated with all four channels OPERABLE.

To confirm that no change in tilt has actually occurred, which might cause the QPTR limit to be exceeded, the incore results may be compared against previous flux maps either using the symmetric thimbles as described above or a complete flux map.

Nominally, quadrant tilt from the surveillance should be within 2 percent of the tilt shown by the most recent flux map data.

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

I ATTACIIMENT B-1 Chan2e Summary, Unit 1 Typed Panes Editorial Chances 3/4 1-19 Added the license number, DPR-66, to the top of the page to 3/4 1-20 he consistent with current convention.

3/41-20b Added the license number, DPR-66, to the top of the page to be consistent with current convention and replaced (Con't) with (Continued) following LIMITING CONDITION FOR OPERATION to be consistent with continuation of other specifications.

3/41-20c Added the license number, DPR-66, to the top of the page to 3/4 1-23 be consistent with current convention.

3/41-23a Added the license number, DPR-66, to the top of the page to be consistent with current convention, and removed the phrase (next page is 3/4 2-1) beneath the page number since this is the end of the Section I specifications and is consistent with the other sections.

3/4 2-2 Added the license number, DPR-66, to the top of the page to be consistent with current convention.

3/4 2-11 No additional changes are included.

B 3/4 1-4 Added the license number, DPR-66, to the top of the page to be consistent with current convention.

B 3/4 2-7 No additional changes are included.

- B 3/4 2-10

)

s ATTACHMENT B-2 Chance Summary, Unit 2 Tvoed Panes Editorial Channes 3/4 1-19 Added the license number, NPF-73, to the top of the page to 3/4 1-21 be consistent with current convention.

3/4 1-24 3/4 1-25 3/4 2-2 3/4 2-10 No additional changes are included.

B 3/4 1-5 l

B 3/4 2-7 Added the license number, NPF-73, to the top of the page to be consistent with current convention.

B 3/4 2-9 No additional changes are included.

B 3/4 2-10 l',?U'

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ML20210B877

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