Text

Proposed Tech Specs Pages for LARs 262 & 135
	ML20196F019
Person / Time
Site:	Beaver Valley
Issue date:	06/17/1999
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20196F013	List: L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages; ML20196F019;
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	NUDOCS 9906290075
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,. ATTACHMENT 262 l

Unit No. 1 Technical specification Paaes l

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9906290075 990617 PDR ADOCK 05000334 P PDR L-

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'- *'- ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical l Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

l Remove Insert 3/4 1-19 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 l 3/4 1-23a 3/4 1-23a l 3/4 2-2 3/4 2-2 l 3/4 2-11 3/4 2-11 l

B 3/4 1-4 B 3/4 1-4 B 3/4'2-2 B 3/4 2-2 B 3/4 2-7 B 3/4 2-7 B 3/4 2-10 B 3/4 2-10 1

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DPR-66 l 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 FQ(Z) and F are verified to be within their limits wit Un 72 I hours.

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 trippable but inoperable due to l 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 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 once per 31 days.

4.1.3.1.2 The position of each full length rod 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 . l

See Special Test Exception 3.10.2 and 3.10.4 1

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

- DPR-66 l

' REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION i 3.1.3.2 The shutdown and control rod position indication system shall be OPERABLE as follows:

Group Demand Counter (1) , 1 per group Individual analog rod instrument channel, 1 per rod )

il2 steps il) accuracy (3) position i I 1 l

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-(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 !

movement information. For power levels below 50%, a 1-hour 1 thermal soak time is allowed before the analog channels are i 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.

6. _m.__m.... _ _ _. . .

DPR-66 l LIMITING CONDITION FOR OPERATION (Continued)

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 l 24 steps in one direction since the last l 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 1 3.0.3 is applicable.

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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 l 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 I

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 2 steps, at least once per 92 days.

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

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

DPR-66 l SURVEILLANCE 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 18 months.

For Core PHYSICS TESTING in Mode 2, primary detector voltage measurements may be used to determine the position of rods in l 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 greater than 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 indicators. To attain thermal equilibrium during the one hour soak time, the absolute value of rod motion shall not 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:

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.

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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

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 K f r 2 1. 0.

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

-DPR-66 l REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 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*#

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 l 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 .

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See special Test Exception 3.10.2 and 3.10.4.

With K.ff 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.

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

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DPR-66 l

POWER DISTRIBUTION LIMITS I

LIMITING CONDITION FOR OPERATION (Continued)

b. THERMAL POWER shall not be increased above 90% of RATED

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

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

SURVEILLANCE REQUIREMENTS 1

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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 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 i band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are l 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 .

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

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

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DPR-66

' POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS

'4.2.4 Verify the QPTR is within the limit:

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

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)

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(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.

I DPR-66 l

'BEACTIVITY CONTROL SYSTEMS i

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.

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.

I For Specification 3.1.3.1 ACTIOli c. and d., it is incumbent upon the f plant to verify the trippability of the inoperable control rod (s). l 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 j the control rod stepping mechanism. In the event the plant is unable j to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under the requirements of ACTION a.

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

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DPR-66 l

' POWER DISTRIBUTION LIMITS 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.

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Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the target band about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at l reduced THERMAL POWER levels. This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking j 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 levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance. i Figure B 3/4 2-1 shows a typical monthly target band near the beginning of core life. j i

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

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DPR-66

P_QWER DISTRIBUTION LIMITS i

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

kQQ.

The QPTR limit of 1.02, at which corrective action is required, provides a margin of protection for both the DNB ratio and linear 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 (F AH) is Possibly challenged.

APPLICABILITY The QPTR 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.

Applicability in MODE 1 less than or equal to 50 percent RTP and in !

other MODES is not required because there is either insufficient l 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) LOOS 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 sufficient 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.

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

DPR-66

' POWER DISTRIBUTION LIMITS BASES

- 3/4.2.4 OUADRANT POWER TILT RATIO (OPTR) (Continuedi SURVEILLANCE REQUIREMENTS (SR)

SR 4.2.4.a l SR 4.2.4.a is modified by a Note that allows QPTR to be calculated l 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 l

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. )

For those causes of'QPT that occur quickly (e.g., a dropped rod), I l l there typically are other indications of abnormality that prompt a verification of core power tilt.

SR 4.2.4.b {

l l 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 l 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 l

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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.

Remove Insert 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 2-2 B 3/4 2-2 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 l

'BE&CTIVITY CONTROL SYSTEMS I 1

l LIMITING CONDITION FOR OPERAT70N (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 movable incore detectors and Fg(Z) and F{g are 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 analyzed results of these accidents remain valid for the duration of operation under these I

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

NPF-73 l

. REACTIVITY CONTROL SYSTEMS I POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Fasition Indication System shall be OPERABLE and capable of rlntermining 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 pocition, 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 s 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 steps 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 l

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

,NPF-73 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:

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 inoparable 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

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 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 1

See Special Test Exception 3.10.2 and 3.10.3.

With K.gr 2 1. 0.

BEAVER VALLEY - UNIT 2 3/4 1-25 Amendment No.

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,NPF-73 l POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) !

ACTION: (Continued) j i

b. THERMAL POWER shall not be increased above 90 percent of RATED THERMAL POWER unless the indicated AFD in within the i target band and ACTION a.2.a)1), above has been satisfied. j

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 above 15 percent 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: l

a. One-minute 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.

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

NPF-73 l

+ POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4 Verify the QPTR is within the limit:

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

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 1

I (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-73

. REAC'TIVITY CONTROL SYSTEMS i

BASES i 3/4.1.2 BORATION SYSTEMS (Continued) satisfied before the verification is completed to ensure that no unacceptable reduction of SHUTDOWN MARGIN occurred when the Lc0 requirements were not satisfied.

The primary function of the surveillance is to ensure that the i valve (s) - used _ to isolate the Primary Grade Water System are locked, sealed or otherwise secured. The frequency of 31 days to ensure that l the Primary Grade Water System is properly isolated is based on engineering judgment, and has proven to be acceptable. Operating 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 g Water System following a. planned activity requiring its use. l 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 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 requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod

-requires measurement of peaking iactors 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.

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

greater than or equal to 541*F and with Measurement all reactor with TaY coolan BEAVER VALLEY - UNIT 2 B 3/4 1-5 Amendment No.

,NPF ,73 l

. POWER DISTRIBUTION LIMITS BASEC .

- =-__

JQ(IAL FLUX DIFFERENCE (AFD) (Continued) 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 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 levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

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

3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS F 9(Z) andF{H 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 hot channel factor limits are maintained provided:

a. Control rods in a single group move together with no individual rod 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 Specification 3.1.3.6.

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

7 l

,NPF .73 l l POWER DISTRIBUTION LIMITS t

_BA _SES ,n -_ - -_ - __

3/4.2.4 OUADRANT POWER TILT RATIO (OPTR) (Continued)

APPLICABILITY (Continued) $

the reactor coolant to require the implementation of a QPTR limit on i the distribution of core power. The QPTR limit g these conditions )

is, therefore, not important. Note that the F an 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 sufficient time to identify the cause and correct the tilt. Note that the power reduction itself may cause a change in the tilted condition.

h. 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.

g. The peaking factors F"AH and Fg(Z) are of primary importance in ensuring that the power distribution remains consistent with the initial conditions used gn the safety analyses. Performing 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 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 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 above its specified limit, the peaking factor surveiglances are required each 7 days thereafter to evaluate F as 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 -

I 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., i 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 i and the core returned to power. l

g. If ACTIONS a through- f are not completed within their associated 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is reasonable, based on operating experience regarding the amount of time required to reach the reduced power level without challenging plant systems.

SURVEILLANCE REQUIREMENTS (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 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) (Continuedl SURVEIT.TANCE REOUIREMENTS (SR) (Continued)

For those causes of QPT that occur quickly (e.g., a dropped rod), j there typically are other indications of abnormality that prompt 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 moveable incore detectors aa used to confirm that the normalized symmetric power distributip. .ts consistent with the indicated QPTR and any previous data indic& ting 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 fu]1 core flux map, 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.

l B 3/4 2-10 Amendment No.

~

BEAVER VALLEY - UNIT 2

ATTACHMENT B-1 Channe Summary. Unit 1 Typed Panes Editorial Channes 3/4 1-19 Added the license number, DPR-66, to the top of the page to be consistent with current convention and in Action "d" corrected a spelling error by replacing (tripable) with (trippable).

3/4 1-20 Added the license number, DPR-66, to the top of the page to be 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, replaced "or" with "of" in the second line of Action b to be consistent with Unit 2, added a period following

and # notes to be consistent with other notes, 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.

3/42-2 Added the license number, DPR-66, to the top of th pcge to be consistent with current convention.

3/4 2-11 Capitalized the word " operable" in Note (3) since .nis is a defined term.

B 3/4 1-4 Added the license number, DPR-66, to the top of the page to B 3/4 2-2 be consistent with current convention.

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

B 3/4 2-10 Capitalized the word " operable" in the first paragraph of SR 4.2.4.b since this is a defined tenn.

i-

~

ATTACHMENT B-2 Channe Summary. Unit 2 Tvoed Pages 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. j 3/4 1-24 Added the license number, NPF-73, to the top of the page to 3/4 1-25 be consistent with current convention and added a period following the

and # notes to be consistent with other notes.

3/42-2 Added the license number, NPF-73, to the top of the page to l be consistent with current convention. j 3/4 2-10 Capitalized the word " operable" in Note (3) since this is a defined term.

B 3/4 1-5 No additional changes are included.

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

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

B 3/4 2-10 Capitalized the word " operable" in the first paragraph of SR 4.2.4.b since this is a defined term.

1

ML20196F019

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