ML20078N270

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Proposed TS 3.3.2.1, Control Rod Block Instrumentation
ML20078N270
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/10/1995
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20078N264 List:
References
NUDOCS 9502150247
Download: ML20078N270 (11)
v • d • e


Text

I Attachment 3 to U-602406 LS-95-001 Page1of5 Attached Marked-Up Pages of the Technical Specifications l

9502150247 950210 l PDR ADOCK 05000461 1 P PDR

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At tachment: 3 to U-602406 i g& e6 , 'LS-95-001 f I P ro v.'AcJ fo r Centrol Rod BloEE Insfrukentation 1

4gw ch, 3.3.2.1 I L

3.3 INSTROMENTATION 3.3.2.1 Control Rod Block Instrumentation 1 LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod A.1 Suspend control rod Immediately  :

withdrawal limiter withdrawal. '

(RWL) channels inoperable. -

J

) B. One or more rod B.1 Suspend control rod Immediately '

pattern controller movement except by channels inoperable. scram.  !

l i'

C. One or more Reactor C.1 Suspend control rod Immediately Mode Switch-Shutdown withdrawal.

Position channels inoperable. A!QN C.2 ' Initiate action to Immediately )

fully insert all insertable control rods in core cells containing one or more fuel assemblies.

CLINTON 3.3-15 Amendment No. 95 I

Attachment 3 to U-602406 LS-95-001 Control Rod Block Instrumentation

, 3.3.2.1 SURVEILLANCE REQUIREMENTS

NOTES------------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains control rod block capability.

4 SURVEILLANCE FREQUENCY SR 3.3.2.1.1 ------------------NOTE-------------------

Not required to be performed until I hour after THERMAL POWE3 is > 7^% RTP- .

':fren WA SW.4. big o pwsf..Tcipdbn(* &er. Pf5fD.

Perform CHANNEL FUNCTIONAL TEST. 92 days 4

N SR 3.3.2.1.2 ------------------NOTE------------------- ,

Not required to be performed until I hour after THERMAL POWER is > 35% RTP and

70% RTA less %n or eqM to N RWLHPR l Perform CHANNEL FUNCTIONAL TEST. 92 days l

SR 3.3.2.1.3 ------------------NOTE-------------------

Not required to be performed until I hour after any control rod is withdrawn in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days (continued)

CLINTON 3.3-16 Amendment No. 95 l I

l 4

. _ _ . , . - --..m. ,. _ . . .

Attachment 3 to U-602406

) - e!s , LS-95-001 i

O CMgb#'

f(MM Centrol Rod Bl$8ft'Ihsffu5entation i i AbrMM .

3.3.2.1 l l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLAK.E FREQUENCY t

SR 3.3.2.1.4 ------------------NOTE-------------------

Not required to be performed until I hour  ;

after THERMAL POWER is s 20% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days

~ ,

SR 3.3.2.1.5 Calibrate the low power setpoint analog 92 days _.

trip modules. The Allowable Value shall i be > 20% RTP and s 35% RTP.

I SR 3.3.2.1.6 Verify the RWL high power Function is not 92 days bypassed when THERMAL POWER is > 70% RTP.

1 SR 3.3.2.1.7 Perform CHANNEL CALIBRATION. 18 months I

SR 3.3.2.1.8 ------------------NOTE-------------------

Not required to be performed until I hour after reactor mode switch is in the shutdown position. ,

Perform CHANNEL FUNCTIONAL TEST.- 18 months SR 3.3.2.1.9 Verify the bypassing and movement of Prior to and ,

control rods required to be bypassed in during the Rod Action Control System (RACS) is in movement of 1 conformance with applicable analyses by a control rods second licensed operator or other bypassed in qualified member of the technical staff. RACS  !

l CLINTON 3.3-17 Amendment No. 95 l

Attachment 3 to U-602405

  • LS-95-001 Page 5 of 5 Control Rod Block Instrumentation 3.3.2.1 m

Table 3.3.2.1 1 (page 1 of 1)

Control Rod Stock Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. Rod Pattern Control system
e. Rod withdrawat tielter (a) 2 st 3.3.2.1.1 SR 3.3.2.1.6 SR 3.3.2.1.9 (b) 2 st 3.3.2.1.2 SR 3.3.2.1.5 sR 3.3.2.1.7 st 3.3.2.1.9
b. Rod pattern controtter 1f83,2 2 SR 3.3.2.1.3 sa 3.3.2.1.4 st 3.3.2.1.5 sa 3.3.2.1.7 st 3.3.2.1.9
2. Reactor Mode switch-shutdown Position (d) 2 st 3.3.2.1.8 I

(e) THERMAL POWER 4 W ;U. c3 e re % n PNL HPSP.

(b) THERMAL POWER > 35% RTP and ; = """. lts5 % n of qued 6 W R w L k P s P. 3 (c) With THERMAL POWER s 20% RTP.

(d) Reactor mode sultch in the shutdown position.

1 l

i l

i l

CLINTON 3.3-18 Amendment No. 95

'i Attachm:nt 4 to U-602406 LS-95-001 Page I of 6 Attached Marked-Up Pages of the Technical Specifications Bases i

l 1

Attachment 4 to U-602406 l LS-95-001 Control Rod Block Instrb*nEntatNn l B 3.3.2.1 '

BASES BACKGROUND The purpose of the RPC is to ensure control rod patterns (continued) during startup are such that only specified control rod sequences and relative positions are allowed over the operating range from all control rods inserted to 20% RTP.

The sequences effectively limit the potential amount and rate of reactivity increase during a CRDA. The RPC, in conjunction with the RCIS, will initiate control rod withdrawal and insert blocks when the actual sequence deviates beyond allowances from the specified sequence. The rod block logic circuitry is the same as that described above. The RPC also uses the turbine first stage pressure

'to determine when reactor power is above the power at which the RPC is automatically bypassed (Ref.1).

With the reactor mode switch in the shutdown position, a control rod withdrawal block is applied to all control rods to ensure that the shutdown condition is maintained. This function prevents criticality resulting from inadvertent control rod withdrawal during MODE 3 or 4, or during MODE 5 when the reactor mode switch is required to be in the shutdown position. The reactor mode switch has two channels, with each providing inputs into a separate rod block circuit. A rod block in either circuit ~will provide a control rod block to all control rods.

APPLICABLE 1.a. Rod Withdrawal Limiter SAFETY ANALYSES, LCO, and The RWL is designed to prevent violation of the MCPR SL APPLICABILITY and the cladding 1% plastic strain fuel design limit that  :

may result from a single control rod withdrawal error (RWE) '

event. The analytical methods and assumptions used in i evaluating the RWE event are summarized in Reference 2. A statistical analysis of RWE events was performed to determine the MCPR response as a function of withdrawal distance and initial operating conditions. From these responses, the fuel thermal performance was determined as a function of RWL allowable control rod withdrawal distance and power level.

The RWL satisfies Criterion 3 of the NRC Policy Statement.

Two channels of the RWL are available and are required to be OPERABLE to ensure that no single instrument failure can i preclude a rod block from this Function.g (continued).

The N L h:4h power RocRon chnnek an. censidered open?Asts 4 conwei roJ votNhawod is 1 mifec0 to no moal %ar) two nofthes,

'The Rwt iow power fvnckon c ha when (Con W red w%chawd M H mM,nne8 to arc-no cons Mered mort  % nO%w PER68tE notches J CLINTON B 3.3-41 Revision No. 7, I

Attachment 4 to U-602406

~ ' LS-95-001 NO Cba M 65 Page 3 of 6 M fo v M e b V' Control Rod Block Instrumentation

\nforM'rACh. B 3.3.2.1 BASES APPLICABLE 1.a. Rod Withdrawal Limiter (continued)

SAFETY ANALYSES, LCO, and Nominal trip set points are specified in the setpoint APPLICA31LITY calculations. The nominal setpoints are selected to ensure that the setpoints do not exceed the Allowable Values ,

between successive CHANNEL CALIBRATIONS. Operation with a 1 trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value, is acceptable.

Trip setpoints are those predetermined values of output at which an action should take place. The setpoints are compared to the actual process parameter (e.g., reactor l power), and when the measured output value of the process l parameter exceeds the setpoint, the associated device (e.g.,

analog trip module) changes state. The analytic limits are derived from the limiting values of the process parameters obtained from the safety analysis. The Allowable Values are derived from the analytic limits, corrected for calibration, ,

process, and some of the instrument errors. The trip ,

setpoints are then determined accounting for the remaining l instrument errors (e.g., drift). The trip setpoints derived in this manner provide adequate protection because instrumentation uncertainties, process effects, calibration tolerances, instrument drive, and severe environment errors ,

(for channels that must function in harsh environments as defined by 10 CFR 50.49) are accounted for.

The RWL is assumed to mitigate the consequences of an RWE event when operating > 35% RTP. Below this power level, the consequences of an RWE event will not exceed the MCPR, and ,

therefore the RWL is not required to be OPERABLE (Ref. 3).

1 1.b. Rod Pattern Controller The RPC enforces the banked position withdrawal sequence (BPWS) to ensure that the initial conditions of the CRDA analysis are not violated. The analytical methods and assumptions used in evaluating the CRDA are summarized in References 4 and 5. The BPWS requires that control rods be moved in groups, with all control rods assigned to a specific group required to be within specified banked positions. Requirements that the control rod sequence is in compliance with BPWS are specified in LC0 3.1.6, " Control Rod Pattern."

(continued) i CLINTON B 3.3-42 Revision No. 0

  • 1_ _----- _

. . LS-95-001 l Page 4 of 6 Control Rod Block Instrumentation

, B 3.3.2.1 BASES ACTIONS C.1 and C.2 -

(continued)

If one Reactor Mode Switch-Shutdown Positisn control rod withdrawal block channel is inoperable. t'ne remaining OPERABLE channel.is adequate to perfccm the control rod withdrawal block function. Required Action C.1 and Required j Action C.2 are consistent with che normal action of an OPERABLE Reactor Mode Switch-Shutdown Position Function to i maintain all control rods inserted. Therefore, there is no I distinction between Required Actions for the Conditions of -l one or two channels inoperable. In both cues (one or both  ;

channels inoperable), suspending all centrol rod withdrawal '

immediately, and immediately initiatirg actica to fully insert all insertable control rods in core cells containing

, one or more fuel assemblies will ensure th n the core is subcritical, with adequate SOM ensured by i.00 3.1.1,

" SHUTDOWN MARGIN (SDM)." Control rods in core cells. J containing no fuel assemblies do not affect the reactivity of the core and are therefore not required to be inserted. -

Action must continue until all insertable control rods in I core cells containing one or more fuel assemblies are fully  !

inserted. ,

1 SURVEILLANCE As noted at the beginning of the SR, the SRs for each  ;

REQUIREMENTS Control Rod Block instrumentation Function are found in the  :

SRs column of Table 3.3.2.1-1. ,

. t The Surveillances are also modified by a Note to indicate l that when a channel is placed ir. an inoperable status solely  :

for performance of required Surveillances, entry into l GR 3.3 2.\ . ) associated Conditions and Required Actions may be delayed  !

for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, provided the associated Function ggMgeyg the maintains control rod block capability. Upon completion of  ;

OP NoWO *gg lthe Surveillance, or expiration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance, the ,

channel must be returned to OPERABLE status or the .

.p mit of M Mpnd applicable Condition entered and Required Actions taken. l Sit 3 3 ' l'1 v"th< l SR 3.3.2.1.1. SR 3.3.2.1.2. SR 3.3.2.1.3. and 3.3.2.1.4 I ()TbOF#" .cotch N SR N *J );m3 The CHANNEL FUNCTIONAL TESTS for the RPC and RWL are performed by attempting to withdraw a control rod not in i oG h DML N 1 compliance with the prescribed sequence and verifying that a l 3'b t,g ,g oA SR l control rod block occurs. A. Any setpoint adjustment shall be {  ;

l W 'q y 1 hop consistent with the assumptions of the current plant specific setpoint methodology. As noted, the SRs are not

% (continued)

CLINTON B 3.3-45 RevisionNo.g  :

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e ,

, LS-95-001 Page 5 of 6 Control Rod Block Instrumentation ,

B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.1. SR 3.3.2.1.2. SR 3.3.2.1.3. and REQUIREMENTS SR 3.3.2.1.4 (continued) required to be performed until I hour after specified conditions are met (e.g., after any control rod is withdrawn in MODE 2). This allows entry into the appropriate conditions needed to perform the required SRs. The  :

Frequencies are based on reliability analysis (Ref. 6).

SR 3.3.2.1.5 The LPSP is the point at which the RPCS makes the transition-between the function of the RPC and the RWL. This transition point is automatically varied as a function of .

power. This power level is inferred from the first stage turbine pressure (one channel to each trip system). These ,

power setpoints must be verified periodically to be within j the Allowable Values. If any LPSP is nonconservative, then the affected Functions are considered inoperable. Since ,

this channel has both upper and lower required limits, it is l not allowed to be placed in a condition to enable either the RPC or RWL Function. Because main turbine bypass steam flow can affect the LPSP nonconservatively for the RWL, the RWL >

is considered inoperable with any main turbine bypass valves '

open. The Frequency of 92 days is based on the setpoint j methodology utilized for these channels.

SR 3.3.2.1.6 [

t i This SR ensures the high power function of the RWL is not .

I 7707e U.f bypassed when power 1si de": the " PSP. The power level is l inferred from turbine first stage pressure signals.

i 7 Periodic testing of the HPSP channels is required to verify  ;

thel.et,.4,,t to be less than or equal to the limit.

{@5P J Adequate margins in accordance with setpoint methodologies l  !

are included. If the HPSP is nonconservative, then the RWL is considered inoperable. Alternatively, the HPSP can be

{

placed in the conservative condition (nonbypass). If placed [

in the nonbypassed condition, the SR is met and the RWL f would not be considered inoperable. Because main turbine  !

bypass steam flow can affect the HPSP nonconservatively for l the RWL, the RWL is considered inoperable with any main

  • turbine bypass valve open. The Frequency of 92 days is based on the setpoint methodology utilized for these '

channels.

t (continued) {

CLINTON 8 3.3-46 Revision No. g I

f , Attachment 4 to U-602406

, LS-95-001

~

b b T) d, P f6 I ControlRodBlo$ke6InsErumentation g

r rN? e < B 3.3.2.1

' \ r$sr&h% 0 .

4

,3 l BASES i

SURVEILLANCE SR 3.3.2.1.9 (continued)

REQUIREMENTS adjustment of control rod speed. To ensure the proper bypassing and movement of those affected control rods, a second licensed operator or other qualified member of the technical staff must verify the bypassing and movement of these control rods is in conformance with applicable analyses. Compliance with this SR allows the RPC and RWL to be OPERABLE with these control rods bypassed.

REFERENCES 1. USAR, Section 7.6.1.7.

2. USAR, Section 15.4.2.
3. NEDE-24011-P-A, " General Electric Standard Application for Reload Fuel" (latest approved revision).
4. NED0-21231, " Banked Position Withdrawal Sequence,"

January 1977.

5. NRC SER, Acceptance of Referencing of Licensing '

Topical Report NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel, Revision 8,  ;

Amendment 17," December 27, 1987.  ;

6. NEDC-30851-P-A, " Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

p i

CLINTON B 3.3-48 Revision No. 0 1

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