ML18092A855

Proposed Tech Spec Changes,Improving Method of Calibr of Analog Rod Position Indication Sys.Significant Hazards Consideration Evaluation Encl

ML18092A855
Person / Time
Site:	Salem
Issue date:	10/16/1985
From:	Public Service Enterprise Group
To:
Shared Package
ML18092A854	List: ML18092A853 ML18092A855
References
NUDOCS 8510220265
Download: ML18092A855 (36)

Text

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PROPOSED CHANGE 'IO TEXllNICAL SPEX:IFICATIONS SALEM GENERATING Sl'ATION UNIT NOS. 1 AND 2 Ref: I.CR 85-12 Description of Change Using the attached revised pages, modify Salem 1 Technical Specifications as follows:

Replace 3.1.3.l through 4.1.3.2 with the attached revised Tech Specs 3.1.3.1 through 4.1.3.2.2.

Tech Specs 3.1.3.3 through 4.1.3.3 remain unchanged.

Replace 3.1.3.4 through 4.1.3.S with the attached revised Tech Specs 3.1.3.4 through 4.1.3.S.

Tech Spec Figures 3.1-1 and 3.1-2 remain unChanged.

Replace Bases 3/4.1.3 with the attached revised Bases 3/4.1.3.

Using the attached revised pages, also nodify Salem 2 Technical

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j Specifications as follows:

Replace 3.1.3.1 through 4.1.3~2.2 with the attached revised Tech Specs 3.1.3.1 through 4.1.3.2.2.

Tech Spec 3.1.3.3 through 4.1.3.3 remain unchanged.

Replace 3.1.3.4 through 4.1.3.S with the attached revised Tech Specs 3.1.3.4 through 4.1.3.S.

Tech.Spec Figures 3.1-1 and 3.1-2 remain unchanged.

Replace Bases 3/4.1.3 with the attached revised Bases 3/4.1.~.

Reason for Change The purpose of these proposed.Technical specification changes is to improve the methcrl of calibration of the Analog Rod Position

• Indication (ARPI) system by providing rcore realistic operational requirements consistent with the real safety requirements qf the ARPI system. 'Ihese proposed changes are nodeled on the revised Technical Specifications provided by westinghouse in their July 23, 1981 letter, attached.

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ADOCK 0 PDR .

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R~f: I.CR 85-12 Significant Hazards Consideration Evaluation The proposed Technical Specification changes are based on the following conclusions:

• Shutdown Banks and Control Banks A and B positions need to be known accurately in a ve-ry limited range, near the top and bottan of the core. Accurate knowledge of these bank positions permits the operator to verify that the control rods in these banks are either fully withdrawn or fully inserted, the normal operating mJdes.for these banks.

Knowledge of these bank positions in these t~ areas satisfies all accident analysis assumptions concerning their position.

Recognizing that the Analog Rod Position Indication (ARP!)

is very temperature sensitive, immediate verification of position after ra:l movement is shifted (in the revised Technical Specifications) fran the ARP! to the group step counters with subsequent verification by the ARP! after temperature equilibration. Canparison of the group demand counters to the bank insertion limits with verification of rod position with the ARP! (after thermal soak after rod motion) is sufficient verification that the control rods are above the insertion limits as assuned in the accident analyses.

Qperation of the Salem Units in accordance with the proposed ARP!

Technical Specification changes:

Would not involve a srgnificant increase in the probability or consequences of an accident previously evaluated for the

• Salem Units, since there are no changes to conditions assuned in the accident analyses.

In-no way creates the possibility of a new or different kind of accident fran any accident previously evaluated for the Salem Units, since no plant modifications resulted fran this change.

D:>es not involve a significant reduction in a margin of

- safety, since there are no changes to conditions assumed in the accident analyses.

Based on the above, we have determined that this change request involves no significant hazards consideration.under 10CFRS0.92.

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REVISED PAGES - UNIT NO. 1

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REACTIVITY CONTROL. SYSTEMS

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i 3/4.1.3 MOVABLE CONTROL ASSEMBLIES

/ GROUP HEIGHT

• LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods, shall be OPERABLE and positioned within + 12 steps (indicated position)' of their group step counter demand position within one _hour after rod notion.

I APPLICABILITY: MODES l* and 2*

ACTION:

a. With one or nnre full length rods inoperable due to being imITDvable as a result of excessive friction or 1TEchanical interference or. kno~n to be untrippable, determine that the SHUTDO\IM 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 rm re than one full length rod inoperable or mis-aligned from l the group step counter demand position by JTDre than + 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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__ ,.-- ..*.. c. With one full length rod inoperable due to causes 9ther than f, ") addressed by ACTION a, above, or mis-aligned from its group step counter demand position by nnre than + 12 steps (indicated position), POWER OPERATION may continue provided that within one hour either:

1. The rod is restored to OPERABLE status withi 11 the above

• alignment requirements, or

2. The remainder of the rods in the bank with the inoperable rod are aligned to within+ 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 3.1.3.5 during *

~ubsequent operation, or

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

• See Special Test Exceptions 3.10.2 and 3.10.3.*

SALEM - UNIT 1 3/4 1-18

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a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days;.this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

b) The SHUTDO~ W\RGIN 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 rmvable incore detectors cind Fo(Z) and F~H are* verified to be .within their limits -within 7Z hours.

• d) The THERMAL PO~R level is reduced.to less than or equal to 75%

of RATED THERMAL PO\\ER within one l'nur 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 PO W£R

• THERMAL PO W£R sha 11 be maintained less than or equal to 75% of RATED THERMAL POW£R until compliance with ACTIONS 3 .1.3 .1.c .3 .a and 3 .1.3 .Le .3 .c above are *

• derronstrated.

SURVEILLANCE RE QJlREMENTS 4.1.3.1.1 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (allowing for one hour thermal soak after rod rmtion) 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 />.

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\_ __ j 4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by rrovement of at least 10 steps in any one direction at least once per 31 days.

SALEM - UN IT -1 3/4 l-18a

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TABLE 3 .1-1 ACCIDENT ANALYSES REQJIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics Rod *c1uster.~ontrol Assembly Mis-alignment Loss Of Reactor Cool ant From Ruptured* Pipes Or From Cracks In Large Pipes M'lich Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Fbwer Major Reactor Coolant System Pipe Ruptures (Loss Of ~oolant Accident)

Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism I-busing (Ro~ Cluster Control Assembly Ejection)

SALEM - UN IT 1 3/4 1-18b

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REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2.l The shutdown and control rod positi_on indication systems shall be OPERABLE and *capable of determining the actu~l and demanded rod positions as fallows: * -

a. Analog rod position indicators, within one tiour after rod JTOtion (allowance for thermal soak-);

All Shutdown Banks: + 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-228 steps.

Contra 1 Bank A: + 12 steps of the group demand counters for withdrawal r~nges-of 0-30 steps and 200-228 steps.

Control Bank B: + 12 steps of the group demand counters for withdrawal ranges-of 0-30 steps and 160-228 steps.

Control Banks C and D: _! 12 steps of the group demand counters for withdrawal range of 0-228 steps.

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b. Group demand counters; + 2 steps of the pulsed output of the

\. Sl a*ve Cycle'r *circuit over the withdrawal range of 0-228 steps.

APPLICABILITY: MODES 1 and 2 *.

ACTION:

a. With a maximum of one analog rod position* indicator per bank inoperable either:

1. Determine the position of the non-indicating rod(s) indirectly by the JTOvable 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 within one oour after any nntion of the "TlOn-indicating rod which exceeds 24 steps in one direction since the* last determination of the rod's position, or

2. Reduce THERMAL PO~R to less than 50% of RATED THERMAL PO\.ER 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 I inoperable either:

SALEM - UNIT 1 3/4 1-19

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• 9

1. Verify that al 1 analog rod position indicators for the

(-------\ affected bank are OPERABLE and that the rmst withdrawn rod

\., __ ..-*** and the least withdrawn rod of the.bank are within a maximum of l~ steps_ 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 PO!iER .to less than 50% of RATED THERMAL POWER -

within 8 !"ours.

SURVEILLANC'E RE QJIREMENTS 4.1.3.2.1.1 Each analog rod µOsition _indicator shall be determined to be OPERABLE by verify.ing that the demand position indication system and the rod position indication system agree within 12 steps (allowing for one hour thermal soak after rod rmtion).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 />.

4.1.3.2.L2 Each of the.above required rod position itidicator(s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least once per 18 rmnths *

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SALEM - UN IT 1 3/4 l-19a

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REACTIVITY CONTROL SYSTEMS

( . ) POSITION INDICATION SYSTEM SHUTDO\o.N LIMITING CONDITION FOR OPERATION 3.1.3.2.2 The group demand position indicator shall be OPERABLE for each shutdown and control rod not fully inserted.

APPLICABILITY: MODES 3*#, 4*#, and 5*#

ACTION:

With less than the above required group demand position indicator(s)

OPERABLE, either:

a. Cease rod ITDtion and*return the *required bank demand position.

indicator(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; or

b. Open the reactor trip system breakers.

SURVEILLANCE REQJIREMENTS 4.1.3.2.2 Each of the above required group demand position indicator(s) shall be determined to be O.PERABLE by ITDvement of the associated mntrol rod at least 10 steps in any one directi~n at least once per 31 days.

• With the reactor trip system breakers in the closed position

1. See Special Test Exception 3.10.5 SALEM - .UNIT 1 3/4 1-20

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REACTIVITY CONTROL SYSTEMS

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(. ** ) POSITION INDICATION SYSTEM SHUTDO~

LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be fully withdrawn.

APPLICABILITY:. MODES l*, 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 be inoperable and apply Specifica~ion 3.1.3.1.

SURVEILLANCE REQJIREMENTS

/ 4.1.3.4 Each shutdown rod shall be determined to be fully withdrawn by use

' .__.. ) of ttie group demand eounters, and verified by the analog rod position indicators within one hour after rod rmtion:

a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C, or D during an approach to reactor critically, 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.

• See Special Test Exceptions 3.10.2 and 3.10.3

1. With Ke ff greater than or equal to 1 .o SALEM - UNIT 1 3/4 1-22

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REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTDO\>.N

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LIMITING CONDITION FOR OPERATION 3.1.3.5 The control banks shall be limited in physical insertion as shown in Figures 3.1-1 and 3.1-2.

APPLICABILITY: MODES l*, 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:

a. Restore the control banks to within the limits within t\l<<l hours, or

b. Reduce THERMAL ffiWER within t\l<<l rours to less than or equal to that fraction of RATED THERMAL *ffiWER which is allowed by the bank 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 />.

... **:**-... , SURVEILLANCE REQJIREMENTS 4.1.3.5 The position of each control bank ~.hall 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 within one hour of rod nt>tion, except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least o nee per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• See Special -Test Exceptions 3.10.2 and 3.10.3

1. With Kett greater than or equal to 1.0 SALEM - UNIT 1 3/4 1-23

e.

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifiCations of this section ensure that (1) acceptable power distributfon limits are maintained, (2) the minimum SHUTDOWN MARGIN is majntained, and (3) limit the potential effects of rod mis-alignment 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 po sit ion indicators is defined as being capable of indicating rod position to within+ 12 steps of the bank demand position for a range of positions. For the Shutdown Banks, and Control Bank A this range is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive. This permits the operato.r to verify that the contr~l rods in these banks are either fully withdrawn or fully inserted, the normal operating nodes for these banks. Knowledge of these banks positions in these ranges satisfies all accident analysis assumptions concerning their position. The range for control Bank B is defined as the group demand counter indicated p9sition betw~en 0 and 30 steps withdrawn inclusive, and between 160.an 228 steps withdrawn inclusive. For Control Banks C and D the range is defined as the group demand counter indicated position between 0 and 228 steps withdrawn.

Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (after

( _) thermal soak after rod notion) is sufficient verification that the control rods are above the insertion limits~

• The ACTION statements which permit limited variation from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. Mis-alignment of a rod requires measurement of peaking factors or a restriction in THERMAL PO~R; either of these restrictions provide assurance of fuel rod integrity during continued operation. The reactivity \\Orth of a mis-aligned rod is limited for the remainder of the fuel cycle to prevent.

exceeding the assumption used in the accident analysis.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavg>541°F and with all reactor coolant.pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are 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 nore frequent verifications required if an automatic nonitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

SALEM - UN IT 1 B 3/4 1-4

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REVISED PAGES - UNIT NO. 2

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REACTIVITY CONTROL SYSTEMS

('."-~~\ 3/4 .1.3 MOVABLE CONTROL ASSEMBLIES

• . . . GROUP HEIGHT LIMITING CONDITION FOR OPERATION

• 3.1.3.1 A11 fu11 1ength (shutdown and contro1) rods, shall be OPERABLE and positioned within.+ 12 steps (indicated position) of their group step counter demand position within one hour after rod notion.

APPLICABILIT~: MODES 1* and 2* '

ACTION:

a. With one or nore fu1 l 1ength rods inoperab1e due to being immovab1e as a resu1t of excessive friction or mechanica1 interference or known to be untrippab1e, determine that the SHUTDOWN MARGIN. requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With nore than one fu11 1ength rod inoperab1e or mis-a1igned from the group step counter demand position by 11Dre than .!_ 12 steps J (indicated position), be in HUT 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 fu11 1ength rod i noperab1e due to causes at.her than

(, I

. addressed by ACTION a, above, or mi s-a1 i gned from its group step counter demand position by nore than + 12 steps (indicated position), POhfR OPERATION may continue provided that within one hour either:

1. The rod is restored to OPERABLE status within the above

• a1 i gnment requirements, or

2. The remainder of the rods in the bank with the i noperab1 e rod are a1igned to within+ 12 steps of the inoperab1e rod whi1e maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER 1evel sha11 be restricted pursuant to Specification 3.1.3.5 during

~ubsequent operation, or 3 *' The rod is dec1ared inoperab1e and the SHUTDllWN MARGIN*

requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

• See Specia1 Test Exceptions 3.10.2 and 3.10.3.

SALEM - UNIT 2 3/4 1-13

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a) A.reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

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 ~s obtained from the rrovable incore dete.ctors and Fg(Z) and FAH 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 70%

of RATED THERMAL POWC:R 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 THERM.AL POWC:R. THERMAL PO~R shall ~e.

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 derro nstr ated

• SURVEILLANCE RE~IREMENTS 4.1.3.1.l The P<>sition 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (allowing for one hour thermal soak after rod rrotion) except during time intervals when the Rod Position Deviation Monitor. is

• inoperable, then verify the group posit.ions 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 inserted in the core shall be determined to be OPERABLE by rrovement of at least 10 steps in any one directio.n at least once per 31 days.

SALEM - UN IT 2 3/4 1-14 i

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TABLE 3.1-1

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ACCIDENT ANALYSES RE QJIRING. REEVALUATION IN THE EVENT OF AN INOPERABLE FULL LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Contra 1 Assembly Mis-alignment_

Loss Of Reactor Coolant From Ruptured Pipes Or From Cracks In Large Pipes ltlich Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At_ Full Power Major Reactor Coolant System Pipe Ruptures(Loss O"fCoolant.Accident)

Major Secondary System Pipe Rupture Rupture of a Co ntro 1 Rod Drive Mechanism 1-b using *(Rod Cluster Co ntro 1 Assembly Ejection) j ~ - .

\. I SALEM - UN IT 2 3/4 1-15

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REACTIVITY CONTROL SYSTEMS

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POSITION INDICATION SYSTEMS ~ OPERATING LIMITING CONDITION FOR OPERATION 3_.1.3.2.1 The shutdown and control rod position indication systems shall be OPERABLE* and capable of determining the actual and demanded-rod positions as follows: *

a. Analog rod position indicators, within one hour after rod nution (allowance for thermal soak);

All Shutdown Banks: + _12 steps of the group demand counters for withdrawal ranges of U"-30 steps and 200-228 steps.

• Control Bank A: + 12 steps of the group demand counters for withdrawal ranges-of 0-30 st'eps and 200-228 steps.

Control Bank B: .:t, 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 160-228 steps.

Control Banks C and D: .:t, 12 steps of the grouP. demand counters for withdrawal ran_ge of 0-228 steps.

/ *:-\

b. Group demand counters; .:t. 2 steps of the pulsed output of the

\'**~--) Slave Cycler Circuit over the withdrawal range of 0-228 steps.

APPLICABILITY: MODES l and 2.

ACTION: .

a. Wfth a maximum of .one analog rod position indicator per bank inoperable either:

1. Determine the position of the non-indicating rod(s) indirectly by the nuvable 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. within one hour after any nution 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 POl\ER 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: I SALEM - UNIT 2 3/4 1-16

/

1. Verify that all analog rod posifion indicators for the affected bank are OPERABLE and that the nDSt withdrawn r.od and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at 1east 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 POlrER to less than 50% of RATED THERMAL POliER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 12 steps (allowing for one hour thermal soak after rod nntion) at lea~t 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 />.

4el.3.2.1.2 Each of the above required rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least once per 18 11Dnths.

/.**

..... , ___ . ,/

~

SALEM - UNIT 2 3/.4 l-16a

(

\\., ___ _

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTDO~

LIMITING CONDITION FOR OPERATION 3.1.3.2.2 The group demand position indicator shall be OPERABLE for each shutdown and co ntro 1 rod not fully inserted.

APPLICABILITY: MODES 3*#, 4*#, and 5*#

• ACTION:

With less than the above required group demand position indicator(s)

OPERABLE, either:

ae Cease rod 11Dtion and return the required bank demand position

. indicator(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; or

b. Open the reactor trip system breakers.

SURVEILLANCE REQJIREMENTS

(*** ..

\ , ___ .1 4.1.3.2.2 Each of the above required group demand position indicator(s) shall be determined to be* OPERABLE by 11Dvement of the associated control rod at least. 10 steps in any one direction at least once per 31 days.

• With the reactor trip system bre*akers in the closed position

1. See Special* Test Exception 3.10.5 SALEM - UNIT 2 3/4 1-17

-- -------~-----*--*---------- - ----- **-**-- -------*-----**--- *--------. *--------- - ...

.-*-*-~

REACTIVITY CONTROL SYSTEMS

/ \

\ ' POSITION *INDICATION SYSTEM SHUTDO~

LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be ful_ly withdrawn.

APPLICABILITY: MODES l*, 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 be inoperable and apply Specification 3.1.3;.l.

SURVEILLANCE RE~IREMENTS 4.1.3.4 Each shutdown rod shall be determined to be fully withdrawn by use o.f the group demand counters, and verified by the analog rod position i ridicators within one hour after rod ODtio n:

a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C, or D during an approach 'to reactor critically, 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.

• See Special_Test Exceptions 3.10.2 and 3.10.3

1. With Keff greater than or equal to 1.0 SALEM - UNIT 2

• 3/4 1-19

\

- - - --- - -- ------*------ ~----~--**- -----~---* *-- *-- - ---~--- ----- ------ - - - - - - - -- - --~ .- - ..

r REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTDO~

LIMITING CONDITION FOR OPERATION 3.1.3.5 The control banks shall be limited in physical insertion as shown in Figures 3el-l and *3.1-2.

• APPLICABILITY~ MODES l*, 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:

a. Restore the control banks to within the 1 imits within t'I<<> hours, or

.b. Reduce THERMAL POWER within t\\O hours to less than or equal to that fraction of RATED THERMAL POWER which is al lowed by the bank 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 />.

\ /

SURVEILLANCE REQJIREMENTS

'"**~-***

4 .1.3 .5 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 within one hour of rod 11Dtion, except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least o nee per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• See Special Test Exceptions 3.10.2 and 3.10.3

1. With Keff greater than or equal to 1.0 SALEM - UN IT 2 3/4 1-20

_,::_.- ..:._.._ .____~-.*-----~ -------------**--*------~~-*---- -* - ----*------~---

REACTIVITY CONTROL SYSTEMS

/-:-:*\

\_*.

1 BASES

~~~~~~~~~~~~~~--'.~~~~~~~~~~~~~~~~~

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) limit the potential effects of rod mis-alignment 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 bank demand position for a range of positions. For the Shutdown Banks, and Control Bank A this range is defined as the group demand counter indicated position between O and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive. This permits the operator to verify that the control rods in these banks are either fully withdrawn or fully inserted, the normal operating OlJdes for these banks. Knowledge of these banks positions in

• these ranges satisfies al 1 accident analysis assumptions concerning their

• position. The range for control Bank B is defined as the group demand counter indicated position betw~en 0 and 30 steps withdrawn inclusive, and between 160 an 228 steps withdrawn inclusive. For Control Banks .c and D the range is defined as the group demand counter indicated position between O and *2"28 steps withdrawn.

Comparison of the. group demand counters to the b~nk insertion limits with (I

verification of rod position with the analog rod position indicators (after

\. __ _._.........

thermal soak after rod OlJtion) is sufficient verification that the control rods are above the insertion limits.

The ACTION statements which permit limited variation from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are OEt. Mis-alignment o*f a rod requires nEasurement of peaking factors or a restriction in THERMAL POWER; either of these restr.ictions provide assurance of fuel rod integrity during continued operation. The reactivity \l()rth of a mis-aligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumption used in the accident analysis.

The maximum rod drop time restriction is a>nsistent with the assumed rod drop time used in the accident analyses.. Measurement with Tavg>541°F and with all reactor coolant.. pumps operating ensures that the nEasured drop times will be representative of insert.ion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are 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 OlJre frequent

• verifications required if an automat"ic nnnitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

SALEM - UNIT 2 8 3/4 1-4

-*--**---------'--------.. -----~- .....~-....:...- .... ~--~*-*._,___...__~*-~**-~*-----*--*----____:.. _:..~-~---------**-----*--:--;-*-** --- ..-*---*--------- - --- ***-- -- ---- _...__ _______ ----------*;-***--*

Westinghouse Water Reactor I**""':': .-

Electric Corporation Divisions *~ -. - .. -

. **:* ""!""1 - .: : ... *

• July 23, 1981 P~E-81-35 Mr. R. A. Uderitz, .General Manager Nuclear Production Public Service Electric and Gas Company 80 Park Plaza Newark, New Jersey 07101

Dear Mr. Uderitz:

Public Service Electric and Gas Company Salem Unit No. *1 REVISED ANALOG ROD POSITION INDICATION SYSTEM TECHNICAL SPECIFICATION Attached for your information is the Standardized Technical Specifications revised by Westinghouse to allow con~inued operation by plants with the Analog Rod Position Indication System (ARP!). These specs were revised to address NRC and plant con~erns about th~ accuracy and usefulness of the

.. ~ ---.... ARPI. An operating plant has had difficulty in maintaining the ARP! within

( ' Tech Spec required minimums. Specifically, work was performed allowing an

\ **------- /

increase in the inaccuracy of the APR! and an increase in the i ndi*cated misalignment allowed. However, this work was very plant and cycle specific and is heavily dependent on the size of the DNBR margin present in the cycle design. Recognizing that this method would not allow a generic solution to the problem of large ARPl inaccuracies, work was performed to determine what changes, if any, could be made to the plant Tech Specs to reflect the real safety requirements of the ARPI. After discussion with the NRC the attached suggested revisions were developed.

• Page l of the attachment provides a new defined term to be included in the Tech Spet Definitions section. The term defi~es what will be considered the ARPI 1 s Reference Position. The revised specs are based on the following:

1.

Shutdown Banks and Control A and B positions need to be known accurately in a very limited range, near the top and bottom of the core.

2. Control Banks C and D positions need to be accurately known at the bottom of the core and from somewhat below the Full Power insertion limits c~ 150 steps) to the top of the core.

___. /

____ __:_____*-~- -~_:_ ___ ____________ _______ ----

~. __,_:; -*~

Page 2*

July 23, 1981

3. Recognizing that.the ARP! is very temperature sensitive, immediate verification of position after rod movement is shifted from the ARP! to the group step counters with subsequent verification by the ARP! after temperature equilibration. *

4. Detection of a misaligned rod is primarily limited to Control Banks C and D and through the use of the Reference Position.

Pages 2, 3 and 4 of the attachment present the revised current NRC spec for a misaligned rod. Westinghouse recommends the use of this spec to assure an adequate response to a misaligned rod, including th~ evaluation of the transients listed on page 4. Pages 5 and 6 list the revised accuracy and operability requirements for the ARP! and the group demand counters. Page 7 is a revision of the NRC spec on RPI operability when not critical but with the trip breakers closed. The spec has been revised to place reliance on the group step counters. Pages 8 ~nd 9 ~re revised insertion limit specs noting the use of the group step counters with ARP! verification. Pages 10 and 11 provide revised Bases for the attached Tech Specs revisions. Finally, page 12 provides a typical figure defining the Reference Position for a Control C

• or D Bank and is referenced in the attached Bases.

The attached have beeri informally reviewed by M~ Duenfeld of the Core Performance Branch of the NRC and have been found to be acceptable. The Tech Specs should be included in the plant specific Tech Specs. It 1s believed that the attached will decrease the number of LERs filed and remove some of the problems associated with this system. These recommended changes should be made to your plant Tech Specs as soon as reasonably possible. If you have any questions please contact the undersigned.

• Very truly yours, c:=/~~> F. Noon, Manager Operating Plant Service Eastern Region Attachment cc: H. J. Midura J. Zupko R. D. Rippe T. N. Taylor L. A. Reiter B. E. Hall .

F. Meyer J ..Ori sea 11 D. J. Jagt C. F. Barclay W R. P. Germann E. A. Watjen ~-

_,,/

~ ,,._~-=~-~ :_.__:: :.__ .~~-.-....:** __..:_. _____._____- - - - - - - - - - -

• -----~~----~ :-~-~ --- --- --~----'-~ -

1, **!FERENCE PCS IT1 ON Analog Rod Position Indication System REFERENCE POSITION is defined as:

a. For all Shutdown Banks, Control Banks A and B, and the Part Length Banks; the group demand counter indicated position between O and 30 steps withdrawn inclusive and between 200 and 228 steps withdrawn i ric1usi ve ..

b. For Control Banks C and O; the gr<1uP demand counter indicated position between O and 30 steps withdrawn inclusive and between 150 and 228 steps withdrawn inclusive. For the withdrawal range of 31 to 14~ steps inclusive the REFERENCE POSITION shall be the individual rod calibration curve noting indicated analog rod position vs indicated group demand counter position.

I

/ l

\..*.. ....*,i

REACTIVITY CONTROL SYSTEMS 3/4. 1.3.MOVABLE CONTROL ASSEMBLIES c*1 GROUP HEIGHT LIMTING CONDITION FOR OPERATION 3.1.3. l All full length (shutdown and control) rods, and all part length rods which _are inserted. in the core, shail be OPERABLE and positioned within :+ 12 steps (indicated-position) of the REFERENCE POSITION corresponding to the group demand counter position within one hour after rod motion.

APPLICABILITY: MODES. l* 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 SHUTDOWN MARGIN require-ment 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 foll or part length rod inoperabie or misaligned

\ ~.-/' from the REFERENCE POSITION by more than :!:. 12 steps (indicated position), be in HOT STANDBY within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s~

c. With one full or part length*rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its REFERENCE POSITION by more than:!:. 12 steps (indicated position), POWER OPERATION may continue provi.ded that within one hour ei.ther:

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:!:. 12 steps of the inoperable rod while . ..

. maintaining the rod sequence and insertion limits of Figures (3.1-1) and(J.1-2); the THERMAL POWER level shall be restricted pursuant to Specification (3.1.3.6) during subsequent operation, or 3; The rod* is declared inoperable and the SHUTDOWN MARGIN require-

. ment of Spe<:if1cation 3.1.1. l is satisfied. POWER OPERATION may then continue provided that:

• See Special Test Exceptions 3.10.2 and 3.10.3.

a) A reevaluation of each accident analysis of Table 3. 1-1

<-.... .. \ is perfonned within 5 days; this reevaluation shall confirm

( *. 'j

• , ,./

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

b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is detennined 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 Fq(Z) and F~H ar~ verified to be within thei~ limits within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s~

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 compl i ance-*wi ACTIONS 3.1.3. l.c.3.a and 3.1.3.1.c.3.c above are demon-th

( strated.

\ .I

• ........ __ .. ;/

SURVEILLANCE *REQUIREMENTS 4.1.3.1.1 The position of each full and part length rod shall be determined to be within ~ 12 steps (indi~ated posi~ion) of the REFERENCE POSITION correspon~ing to the. group demand position at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (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 inserted and each*part length rod which is. 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.

(

\

~-.----

• --- --------~-----*----*----------- --- *----

TABLE 3. 1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL OR PART LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misdlignment Loss Of Reactor Coolant From Small Ruptured Pipes Or From Cr~:* ..

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 Co~lant Accident)

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

.____ ./'

~-STS 3/4 1-16 OCT 1 1976

REACTIVITY CONTROL SYSTEMS POSITION. INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The shutdown, control and part length 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, respectiyely, as follows:

Analog rod position indicators, within one hour after rod motion (allowance for thermal soak);

All Shutdown Banks - :!:,. 12 steps of the group demand counters.

for withdrawal ranges of 0-30 steps and 200-228 steps.

Control Banks A and B - .:!:. 12 steps of the group demand counters for withdrawal ranges of o-30 steps and 200-228 steps.

Control Banks C and D -*.:!:. 12 steps of the group_ demand counters for wi thdrawa 1 ranges of 0-30 steps and 150-228 steps. :, 12.

~

steps of the RE_FERENCE POSITION for withdrawal range of 31-149 steps .

( \

\.

All Part Length Banks - .:t, 12 steps of the group demand counters for withdrawal ra*nges of 0-30 steps and 200-228 steps.

Group demand counters; :, 2 steps APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one analog rod position indicator per bank inoperable either;..

1. Determine the position of the non-indicating rod(s) indirectly 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 within one hour after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination

• of the rod s position, or 1

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 are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 st~ps (corrected indicated pnsiti~n} 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 1.ass tha*n 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 />.

SURVEILLANCE REQUIREMENTS 4.1.3.2.1* Each analog rod position indicator shall be detennined to be OPERABLE by verifying that the demand position indication system and the rod position indica-tion system (by use of the REFERENCE POSITION) agree within 12 steps (allowing for one hour thermal soak after 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 indica-tion system (by use of the REFERENCE POSITION) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. .

4.1.3.2.2 Each of the above required rod position indicator(s) shall be deter-mined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at 1east .

( . \ once per 18 months .

\ /

(

\ ...___ . _,,,..

---

'--*--~-------'--~.,;.._,-**- *_ _

r ..:.::__~~-*

• _, .,_,,_:~ :~~-~-

... :___._ ,_:._ * ._ _ _ _: : *- --- --**---:--*-*-**--* c.- - * - - - - - - - - - - -*-** ** -

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 deter-mining within.:!:, 2 steps the demand position for each shutdown,._control or.part length rod not fully inserted.

APPLICABILITY: MODES 3*#, 4*# and S*#

ACTIONi With less than the above required group demand position indicators(s) OPERABLE, immediately open the reactor trip system breakers.

SURVEILLANCE REQUIREMENTS *.

4.1.3.3 Each of the above required group demand position indicator(s) shall be detenni ned to be OPERABLE by movement of the associated control rod at 1east. l 0

. steps in any one direction at least once per 31 days ..

• With the reactor trip system breakers in the closed position.

1. See Specia1 Test Exception 3.10.S

-*e REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION

• 3.1.3.5 All shutdown rods shall be fully withdrawn.

APPLICABILITY: MODES. l* 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 be inoperable and apply Specification (3.1.3.1).

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn by use of

t. the group demand counters, and verified by the analog rod position indicators

\ . ________,,, ; .

within one hour after rod motion .

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

• See Special Test Exceptions 3.10.2 and 3. 10.3

1. With Keff greater than or equal to 1. O

• . **-~

/

--**-----*-~- .. ____ __ .:__*

_;_ -~'--'-*

REACTIVITY CONTROL SYSTEMS

(°":! CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3ol.3~6 The control banks shall be limited in physical insertion as shown in F~gures (3.1-1) and(3.l-2).

APPLICABILITY:. MODES 1* and 2*#.

ACTION:

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

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 bank 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 />.

\ /

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 <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 indic~tors within 6ne hour of rod motion; except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the indi~idual 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 Exceptions 3.10.2 and 3.10.3

1. With Keff greater than or equal .to 1.0

---

~--*-~~--~*-* - - *___:__* ............ -~---~ .: _______ __ -- --* - ---- -~ -------- --~- ------ -------- --~---

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) limit the potential effect*s of rod mhalignment on assodated _accident an*alyses.

OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the ~antral 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 ~teps of the reference position. F.or the Shutdown Banks, Control Banks A and B, and the Part Length Banks the REFERENCE POSITION is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive. This permits the operator to verify that the control rods in these banks are either fully withdrawn or fully inserted, the normal operating modes for these bariks. Knowledge of these. bank positions in these two areas satisfies all accident analysis assumptions concerning their position. For Control Banks C and 0 the REFERENCE POSITION is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and b~tween 150 and 228 steps withdrawn _inclusive. For the withdrawal range of 31 to 149 steps inclusive the REFERENCE POSITION_is defined as* the iridividual rod calibration curve noting indicated analog rod position vs indicated group demand counter position {Figure B 3/4.1-f). Comparison of the indicated analog rod position to the calibration curve is sufficient .. to allow determination that a control rod is indeed misaligned from its bank. Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators {after thermal soak after rod motion) is sufficient verification that the control rods are above the insertion limits.

-*- _. --------------~- ------~-..:...._---~--~-....._ ---~-------:____:___.

~

..--*--\ RE~CT!VITY CONTROL SYSTEMS BASES The ACTION statements which permit limited variations from the ba~ic requirements are acc:ompanied by additional restrictions which ensure that the oriainal design criteria are met: Misalignment of a rod requires measurement

.Jf peaking factors *and a restriction in iHE~MAL POWER. These restrictions . .

provide ass~;ance of fuel rod integrity during continued operation. In addition, those safety analyses affected by a :nisaligned rod are reevaiuated to confirm that tne results remain valid during future operation.

Control rod positions and OPERABILITY of the rod position indicators are required to oe vt::rtf~ed on a ncminal 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 frequent ~erifications required if an automatic monitoring channel is inoperable.

These verificJtion frequencies are adequate for assuring that the applicable LCO's are satisfied.

(ALTERNATE).

The restric~ion prohibiting.part length r6d insertion ensures that adverse power shcpes anc ~apid loca1 power changes ~hich may aff~ct DNB considerations do net occur as a rasul! ~f part-length rod insertion during operation. *

(--- .. _;

~-STS a 3/4 l-4 StP l Q lSSO

... *- -- .....\

( j

"* _/

Figure B 3/4.1-1 .ANA.100 RPI vs. GROOP DEMAND INDICATED POSITIOO