ML20052E640

Proposed Tech Specs 3/4.1.3.1 Re Movable Control Assemblies & 3/4.1.3.2 Re Position Indication Sys

ML20052E640
Person / Time
Site:	Beaver Valley
Issue date:	05/05/1982
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20052E634	List: ML20052E633 ML20052E640
References
NUDOCS 8205110301
Download: ML20052E640 (13)

Text

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTRJL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods which are inserted in the core, shall be OPERABLE and positioned within i 12 steps (indicated position determined in a:cordance with Specification 3.1.3.2) corresponding to the group demand counter position within one hour af ter rod motion.

APPLICABILITY: MODES 1* and 2*

ACTION:

a. With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUT 00WN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With more than one full length rod inoperable or misaligned from the 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its 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 remainder of the rods in the bank with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figures (3.1-1) and (3.1-2); the THERMAL POWER level shall be restricted pursuant to Specification (3.1.3.6) during subsequent operation, or l 3. The rod is declared inoperable and the SHUTDOWN FMRGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that; a) A reevaluation of each accident analysis of Table 3.1-1 is perfonned 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.

BEAVER VALLEY - UNIT 1 3/4 1-18 PROPOS ED 'dORDI NG B205110301 820505 PDR ADOCK 05000334 P PDR

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.' 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c) A power distribution map is obtained from the movable incore detectors and F0 (Z) and FSH are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour. and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER. THERMAL POWER shall be maintained less than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1.3.1.c.3.a and 3.1.3.1.c.3'.c above are demons tr~a ted.

SURVEILLANCE REQUIREMENTS 4.1.3.1.l' The position of each full length rod shall be determined to be within

+ 12 steps (indicated position) of the group demand position at least once per 12 ;

hours (allowing for one hour thermal soak after rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full length rod not fully in,serted 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.

• See Special Test Exceptions 3.10.2 and 3.10.4 BEAVER VALLEY - Uti1T 1 3/4 1-19 PROPOSED WORDIllG J

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL OR PART LENGTH R00 Rod Cluster Control Assembly Insertion' Cnaracteristics Rod Cluster Control Assembly Misalignment Loss Of Reactor Coolant From Small Ruptured Pipes Or From Cracked Large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor Coolant System Pipe Ruptures (Loss Of Coolant Accident)

Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)

SEAVER VALLEY - UNIT 1 3/4 1-19a PROPOSED WORDING

REACTIVITY C0flTROL SYSTEf45 POSITI0tl IllDICATIOil SYSTEf4S-0PERATIttG LIf41TIflG C0ilDITI0tl FOR OPERATI0tl 3.1.3.2 The shutdown and control individual rod position indication system and the demand position indication system shall be OPERABLE and capable of determining the actual and demanded control rod positions, respectively, as follows:

Analog rod position, within one hour after rod motion (allowance for thermal soak); + 12 steps.

Group Demand Counters; + 2 steps The actual analeg rod position shall be determined by direct analog indication or, as a backup, by measurement of channel detector primary voltages.

If a rod position indicator exceeds the allowed deviation specified above, t od positions for the affected rods shall be determined by measuring detector primary voltages, as follows:

a. Immediately

b. If associated rods move greater than 6 steps (greater than 12 steps if all rods in the group have been determined to be within 6 steps of the group demand indicator by primary voltage measurements within the previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

c. At 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals if the affected rod (s) are not fully inserted or withdrawn

d. At 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> intervals if the affected rod (s) are fully inserted or withdrawn.

BEAVER VALLEY - UtlIT 1 3/4 1-20 PROPOSED WORDIrlG I

, REACTIVITY CONTROL SYSTEMS LIMITING C0flDITION FOR OPERATION (continued)

When the rod position indicator channel is INOPERABLE, the position of not more than three control rods per bank which are not fully inserted or fully withdrawn may be determined by use of the detector primary voltage measurements.*

APPLICABILITY: MODES 1 and 2*

ACTION:

a. With a maximum of three analog rod position indicators per bank INOPERABLE, either:

. 1. Determine the position of the non-indicating rod (s) indirectly j by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 1 within one hour af ter any motion of the non-indicating 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. With a maximum of one group demand position indicator per bank INOPERABLE, either:

1. Verify that all rod position indicators for the affected bank i are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps (corrected indicated position) of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

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

V St_RVEILLANCE REQUIREMENTS

! 4.1.3.2.1 Each analog rod position indicator shall be determined to be OPERASLE by i

verifying that the demand position indication system and the rod position indication system agree within 12 steps (allowing for one hour thermal soak after

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rod motion) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, j For any INOPERABLE channel, no repairs or adjustments shall be permitted without .

being followed inmediately by a full range calibration.

BEAVER VALLEY - UNIT 1 3/4 1-20a PROPOSED WORDING i_

,' REACTIVITY C0f1 TROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.1.3.2.2 Each of the above required rod position indicator (s) shall be 3 determined to be OPERABLE by performance of a CHAtif4EL FullCTIONAL TEST 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 shutdown banks A and B and control banks A-and B for the purpose of satisfying Specification 3.1.3.2. During Mode 2 operations, 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 i 12 steps during reactor startup and shutdown operations, while rods are being withdrawn or inserted.

t If the rod position indicators for shutdown banks A and B and control j banks A and B deviate by greater than i 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 to permit stabilization of the rod position analog indicators.

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BEAVER VALLEY - UillT 1 3/4 1-20b PROPOSED WORDING

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t REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN

LIMITING CONDITION FOR OPERATION 1

3.1.3.3 The group demand position indicator shall be OPERABLE and capable of determining within i 2 steps the demand position for each shutdown or control rod not fully inserted.

APPLICABILITY: MODE 3 with the Reactor Trip Breakers closed ACTION:

l With less than the above required group demand position indicator (s) OPERABLE, verify the ACTION requirements of 3.1.3.2.b are met, or, immediately open the reactor trip system breakers.

, SURVEILLANCE REQUIREMENTS l

4.1.3.3 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at i least once per 18 months.

e BEAVER VALLEY - UNIT 1 3/4 1-21 PROPOSED WORDING l

REACTIVITY CONTROL SYSTEMS R00 DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time I

from the fully withdrawn position shall be <.2.2 seconds from beginning -

of decay of stationary gripper coil voltage to dashpot entry with:

a. T 1 541 F, and avg

b. All reactor coolant pumps operating.

APPLICABILITY: MODE 3.

ACTION:

a. With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b. With the rod drop times within limits but determined with 2 reactor coolant pumps operating, operation may proceed provided THEPyAL POWER is restricted to:

1.

< 61% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are open, or 2,

< 66% of RATED THERFAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.

SURVEILLANCE REQUIREMENTS 4.1. 3. 4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality: l a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and

c. At least once per 18 months.

SEAVER VALLEY - UNIT 1 3/4 1-22 PROPOSED WORDING -

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REACTIVITY C0tiTROL SYSTEMS SHUTDOWN RCD IflSERTION LIMIT i LIMITING C0tlDITION FOR OPERATION i

3.1. 3. 5 All shutdown rods shall be fully withdrawn. l 1

APPLICABILITY: MODES 1* and 2*#

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification (4.1.3.1.2), within one hour either:

a. Fully withdraw the rod, or

b. Declare the rod to t e inoperable and apply Specification (3.1.3.1).

SURVEILLAtlCE REQUIREMEllTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn by use of the group demand counters, and verified by the analog rod position indicators within one hour af ter rod motion.

a. 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

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• See Special Test Exceptions 3.10.2 and 3.10.4 l # With K ef7 1 1.0 h

BEAVER VALLEY - UNIT 1 3/4 1-23 i

PROPOSED WORDING

REACTIVITY __ CONTROL SYSTEMS C0!1 TROL ROD IllSERTI0fl LIMITS _

LIMITIllG C0f1DITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in l Figures (3.1-1) and (3.1-2).

APPLICABILITY: MODES 1* and 2*#.

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification (4.1.3.1.2), either:

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a. Restore the control banks to within the limits within two hours, or

b. Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or

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

S_URVEILLA!!CE REQUIREMEtlTS 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, by use of the group demand counters and verified by the analog rod position indicators, 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• See Special Test Exception 3.10.2 and 3.10.4

1. With Keff g 1.0 BEAVER VALLEY - UNIT 1 3/4 1-23a PROPOSED WORDIIH3

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 The group demand position indicator shall be OPERABLE and capable of determining within + 2 steps the demand position for each shutdown or control rod not fully inserted.

APPLICABILITY: MODE 3 with the Reactor Trip E.eakers closed ACTION:

With less than the above required group demand position indicator (s) OPERABLE, verify the ACTION requirements of 3.1.3.2.b are met, or, immediately open the reactor trip system breakers.

SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.

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I BEAVER VALLEY - UNIT 1 3/4 1-21 PROPOSED WORDING I

.. REACTIVITY CONTROL SYSTEMS l BASES t

i 3/4.l'.2 B0 RATION SYSTEMS (continued) i The boration capability of either system is sufficient to provide a SHUT-DOWN MARGIN from all operating conditions of 1.0% ak/k after xenon decay and cooldown to 200 F. The maximum boration capability requirements occur at ECL from full power equilibrium xenon conditions and requires 11,336 gallons of 7000 ppm borated water from the boric acid storage tanks or 49,917 gallons of 2000 ppm borated water from the refueling water storage tank.

1 With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection j system becomes inoperable.

The boration capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1% Ak/k af ter xenon decay and cooldown from 200 F to 140 F.

This condition requires either 5000 gallons of 7000 ppm borated water from the boric acid storage tanks or 175,000 gallons of 2000 ppm borated water from the refueling water storage tank.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES i

The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses.

OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment

. and insertion limits. OPERABLE condition for the analog rod position indicators is defined as being capable of indicating rod position to within + 12 steps of the associated group demand indicator. The specifications of this section permit

, a one hour stabilization period after rod motion to penait stabilization of known thermal drif t in the rod position analog instruments. The use of rod position indication primary voltage measurements is permitted as a backup to direct reading of the analog indicators. Comparison of the group demand indicator i to the calibration curve is sufficient to allow determination that a control rod is

! indeed misaligned from its bank when primary voltage measurements are used.

Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (af ter thermal soak af ter rod motion) is sufficient verification that the control rods are above the insertion limits.

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BEAVER VALLEY - EMIT 1 B 3/4 1-3 PROPOSED WORDING l

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REACTIVITY CONTROL SYSTEMS i r l

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BASES l.

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The ACTION statements .which perait limited variations from the basic j requirements are accompanied by additional restrictions which ensure that the 1 orininal design criteria are met. Misalignment of a rod requires measurement [

l of peaking factors and a restriction in THERMAL POWER. These restrictions-

,t provide assuranc'e of fuel rod integrity during continued operation. In addition, i those safety analyses affected by a misaligned rod are reevaluated to confira j that the results remain valid during future operation.

! Control rod positions and OPERABILITY of the rod position indicators are  !

j required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more i frequent verifications required if an automatic monitoring channel is inoperable. ,

These verification frequencies are adequate for assuring that the applicable  !

l LCOs are satisfied.  !

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l SEAVER '/ ALLEY - UNIT 1 B 3/4 1-4 PROPOSED WORDING

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