Text

Amend 79 to License NPF-62,clarifying Startup Surveillance Requirements & Establishing Plant Conditions to Perform Surveillances Associated W/Change of Plant Operational Conditions
	ML20046C169
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Site:	Clinton
Issue date:	07/15/1993
From:	Dyer J; Office of Nuclear Reactor Regulation
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p= atog'o UNITED STATES 4

l' NUCLEAR REGULATORY COMMISSION

~

WASHINGT ON, D. C. 20555

\\.....}p ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE. INC.

DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. NPF-62 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated October 30, 1987, August 31, 1990, and August 16, 1991, as supplemented December 20, 1990, and October 17, 1991, complies with the i

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR i

Pas 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:

lllinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

930809c290 930715 PDR ADOCK 05000461 P

PDR

. (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 79, are hereby incorporated into this license.

Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days, i

FOR THE NUCLEAR REGULATORY COMMISSION fffz f JJ ames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of Issuan:a: July 15, 1993 I

3 i

i

..~

ATTACHMENT TO LICENSE AMENDMENT NO. 19 FACILITY OPERATING LICENSE N0. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corre,ponding overleaf pages, as indicated by an asterisk, are provided to inintain document completeness.

Those pages indicated by a double asterisk, are corrected pages from Amendment No. 71.

Remove Paaes Insert Paaes 3/4 3-1*

3/4 3-1*

3/4 3-2 3/4 3-2 3/4 3-7*

3/4 3-7*

3/4 3-8 3/4 3-8 3/4 3-9*

3/4 3-9*

3/4 3-10 3/4 3-10 3/4 3-11**

3/4 3-11**

3/4 3-12*

j 3/4 3-38a**

3/4 3-38a**

3/4 3-63 3/4 3-63 3/4 3-64 3/4 3-64 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-69 3/4 3-70*

3/4 3-70*

j 3/4 3-89*

3/4 3-89*

j 3/4 3-90 3/4 3-90 3/4 3-90a

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION L1H1 TING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE

with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a.

For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdown Position.

3.

With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The provisions of Specification 3.0.4 are not applicable.

2.

With two of the four channels required for any Trip Function incperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already exists. The provisions of Specification 3.0.4 are not applicable.

3.

With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.1-1.

b.

For Reactor Mode Switch Shutdown Position take the ACTION as shown in Table 3.3.1-1.

SURVEILLANCE REOU1REMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.

Reactor protection system divisional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage such that all trip functions are tested at least once every four fuel cycles.

l

A channel cay be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for l

required surveillance provided at least two OPERABLE channels are monitoring that parameter.

I CLINTON'- UNIT 1 3/4 3-1 Amendment No. 71 APR9 1993

INSTRUMENTATION REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS (Continued) 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least two logic trains such that all logic trains are tested at least once per 36 months and one channel per trip function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the Intermediate Range Monitor Surveillance Requirements for entry into OPERATIONAL CONDITION 2 or 3 from Operational Condition 1, provided the surveillances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2 or 3.

B I

i CLINTON - UNIT 1 3/4 3-2 Amendment No.

79

TABtt 3.3.1-2

. b REAC10R PROT _ECTION SYSTEM RESPONSE TIMES 5

g RESPONSE TIME FUNCTIONAL UNIT (Seconds) cz U

l.

Intermediate Range Monitors:

a.

Neutron Flux - High NA b.-

Inoperative-NA 2.

Average Power Range Monitor *:

a.

Neutron Flux -High, Setdown MA

b..

Flow Blased Simulated Thermal Power - High 5 0.09**

c.

-Neutron Flux - High 5 0.09 d.

Inoperative NA 3.

Reactor Vessel Steam Dome Pressure - High 5 0.33 w

4

. Reactor Vessel Water Level - Low, tevel 3 5 1.03 1

S.

Reactor Vessel Water Level - High, tevel 8 s 1.03 w

6.

Main Steam Line Isolation Valve - Closure s 0.04 4

7.

Main Steam Line Radiation - High NA 8.

Drywell Pressure - High NA 9.

Scram Discharge Volume Water Level - High a.

Level Transmitter M

b.

Float Switches M

10.

Turbine Stop Valve - Closure 1 0.04 11.

Turbine Control Valve Fast Closure, Valve Trip System 011' Pressure - Low s 0.05,

12. Reactor Mode Switch Shutdown Position-M g $.

13. Manual Scram M

% =9 eo

Neutron detectors:are exempt from response time testing. Response time shall be measured from the

@g detector output or from'the input of the.first electronic component in the channel.

- Not including a simulated themal power time constant specif bd in the COLR.

Measured from start of turbine control vaive fast closure, w

--.. -~.-.~........... m.--.

-, -. _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

TABLE 4.3.1.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

E CHANNEL OPERATIONAL i

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH g

FUNCTIONAL UNIT CHECK TEST CAllBRATION(d SURVEILLANCE REQUIRED

[

1.

Intermediate Range Monitors:

a.

Neutron Flux - High S/U,S,(b)

W R

2 S

W R

3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor:")

a.

Heutron Flux - High, S/U,S,(b)

W SA 2

Setdown S

W SA 3,4,5 b.

Flow-Biased Simulated

{

Thermal Power - High S

S/U(*), Q W(d"O, SA, R )

1 U

id c.

Neutron Flux - High S

S/U(*), Q W

),

SA 1

{

d.

Inoperative NA Q

NA 1,2,3,4,5 3.

Reactor Vessel Steam Dome 0

Pressure - High S

Q R(O 1, 2 )

4.

Reactor Vessel Water level -

Low, level 3 S

Q R(O 1, 2 5.

Reactor Vessel Water Level -

l High, Level 8 S

Q R(O I

k 6.

Main Steam Line Isolation 5

Valve - Closure NA Q

R 1

x

?

7.

Main Steam Line Radiation -

0 g

High S

Q R

1, 2 )

8.

Drywell Pressure - High S

Q R(O 1, 2")

-a.

a a

Mill E 4.3.1.1.1 (Continiicd)

{

REACTOR PROTECTION SYSTIM INSTRUMENTATION SURVEfttANCE REQUIREMENTS "i

E CilANNEL OPERATIONAL CllANNI E FUNCiIONAL CHANNEL CONDITIONS IN MtICH

}

FUNCTIONAL IMIT CitECK TEST CAtlBRATION(a)

SURVEILLANCE REQUIRED

[

9.

Scram Discharge Volume Water level - Hioh a.

Level Transmitter S

Q RI9) 1, 2, S "I l

I b.

Float Switches MA Q

R 1, 2, SIII 5

Q "I 10.

Turbine stop Valve - Closure M4 R ")

I 1

11.

Turbine Control Valve Fast Closure Valve Trip System 011 gQ,)

Rg,)

g Pressure - Low NA 1

1 4

12.

Reactor b de Switch

[

Shutdown Positten MA R

MA 1,2,3,4,5 E

13.

Manvet Scram NA Q

NA 1,2,3,4,5 l

6 to r*

$F

=

.:t

.-,_m

. -.. ~

,m-<

r..,-t--

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CAllBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least I decade during each controlled shutdown, if not performed within the previous 7 days.

(c) Within 7 days prior to startup.

(d) This calibration shall consist of the adjustment of the AP.RM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER *.

Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

(e) This calibration shall consist of a setpoint verification of the Flow Biased Simulated Thermal Power-High trip function.

The Flow Biased Simulated Thermal-High trip function is verified using a calibrated flow signal.

(f)

The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.

(g) Calibrate the analog trip module at least once per 92 days.

(h) Deleted.

(i) This calibration shall consist of verifying that the simulated thermal power time constant is within the limits specified in the COLR.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

1 (k) With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is

^

not required to be OPERABLE per Special Test Exception 3.10.1.

(m) The CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION shall include the turbine first stage pressure instruments.

The provisions if Specification 4.0.4 are not applicable, provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after exceeding 25% of RATED THERMAL POWER.

CLINTON - UNIT 1 3/4 3-10 Amendment No. 79

INSTRUMENTATION

)

3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.3.2 The containment and reactor vessel isolation control system (CRVICS) channels shown in Table 3.3.2-1 shall be OPERABLE

with their trip setpoints i

set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

i a.

With a CRVICS channel trip setpoint less conservative than the value j

shown in the Allowable Value column of Table 3.3.2-2, declare the channel l

inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

j b.

For CRVICS Main Steam Line Isolation Trip Functions:

1.

With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

The provisions of Specification 3.0.4 are not applicable.

2.

With two of the four channels required for any Trip Function inoperable, place one channel in the tripped condition within six l

hours provided no tripped channel for that Trip Function already exists.

The provisions of Specification 3.0.4 are not applicable.

3.

With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.2-1.

c.

For other CRVICS Isolation Trip Functions:

1.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition ** within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The provisions of Specification 3.0.4 are not applicable.

For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided l

at least two OPERABLE channels are monitoring that parameter.

For other CRVICS Isolation Trip Function, a channel may be placed in an in-operable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided the l

requirements of Table 3.3.2-1 are fulfilled.

l

- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

CLINTON - UNIT 1 3/4 3-11 Amendment No. 71

a INSTRUMENTATION CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING CONDITION FOR OPERATION (Continued) 3.3.2 ACTION (Continued):

2.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system

in the tripped condition within I hour and take the ACTION required by Table 3.3.2-1.

SURVEILLANCE REOUTREMENTS 4.3.2.1 Each CRVICS channel shall be demonstrated OPERABLE by the performance ~

of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

i 4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.

CRVICS main steam line isolation divisional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage. Each of the two trip systems or divisions of the CRVICS trip system logic shall be alternately and manually i

tested independent of the SELF TEST SYSTEM during every other refueling outage.

All manual testing shall be completed such that all trip functions are tested at least once every four fuel cycles.

l 4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 Each test shall include at least one logic train tested at least once conths.

per 36 months, and one channel per trip function such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific CRVICS trip function.

The trip system need not be placed in the tripped condition if this would i

cause the Trip Function to occur. When a trip system can be tripped condition without causing the Trip Function to occur,placed in the place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

CLINTON - UNIT 1 3/4 3-12 Amendment No. 71

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 38 -

With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 39 -

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within I hour *; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 40 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic actuation capability of either Division I or Division II ECCS, and restore the inoperable channel (s) to OPERABLE status within 7 days. Otherwise, declare the associated system (s) inoperable.

ACTION 41 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel (s) to Or RABLE status within 7 c

days. Otherwise, declare the HPCS system inoperable.

The provisions of Specification 3.0.4 are not applicable.

CLINTON - UNIT I 3/4 3-38a Amendment No. 71

INSTRUMENTATION 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION LiHITING CONDITION FOR OPERATION 3.3.6 The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

a.

With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.

SURVElllANCE REQUIREMENTS 4.3.6.1 Each of the above required control rod block trip systems and instru-mentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.

4.3.6.2 The provisions of Specification 4.0.4 are not applicable to the Intermediate Range Monitor and Source Range Monitor Surveillance Requirements for entry into OPERATIONAL CONDITION 2 and 2", respectively, from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2 and 2", respectively.

With IRMs on range 2 or below.

CLINTON - UNIT 1 3/4 3-63 Amendment No. 79

TABLE 3.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION n

C MINIMUM APPLICABLE 5

OPERABLE CHANNELS (e)

OPERATIONAL E

TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION t

g 1.

R0D PATTERN CONTROL SYSTEM U

a.

Low Power Setpoint 2

1, 2 60 b.

RWL High Power Setpoint 2

1 60 2.

APRM a.

Flow Biased Neutron Flux - Upscale 3

1 61 b.

Inoperative 3

1, 2, 5 61 c.

Downscale 3

1 61 d.

Neutron Flux - Upscale, Startup 3

2, 5 61 3.

SOURCE RANGE MONITORS a.

Detector not full in(

3 2'

61 w

2**

5 62 1

b.

Upscale" 3

2' 61 w

2**

5 62 Inoperative "

3 2'

61 l

h c.

2**

5 62 d.

Downscale(*'

3 2'

61 2**

5 62 4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in 6

2, 5 61 b.

Upscale 6

2, 5 61 c.

Inoperative 6

2, 5 61 d.

Downscale(*

6 2, 5 61 5.

SCRAM DISCHARGE VOLUME g

[

a.

Water Level-High 2

1, 2, 5*

64 l

6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW

[

a.

Upscale 3

1 64

?

7.

REACTOR MODE SWITCH M

a.

Shutdown Mode 2

3, 4 63 i

b.

Refuel Mode 2

5 63 i

TABLE 3.3.6-1 (Continued)

CONTROL R0D BLOCK INSTRUMENTATION TABLE NOTATIONS With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2.

With IRMs on range 2 or below.

(a)

This function shall be automatically bypassed if detector count rate is

> 100 cps or the IRM channels are on range 3 or higher.

(b)

This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.

(c)

This function shall be automatically bypassed when the IRM channels are on range 3 or higher.

(d)

This function shall be automatically bypassed when the IRM channels are on range 1.

(e)

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided at least one other OPERABLE channel in the same trip function is monitoring that parameter.

ACTION ACTION 60 - Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2.

ACTION 61 - With the number of OPERABLE Channels:

One less than required by the Minimum OPERABLE Channels per a.

Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.

b.

Two or more less than required by the Minimum OPERABLE Channels per Trip function requirement, place at least one inoperable channel in the tripped condition within I hour.

ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within I hour.

ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

ACTION 64 - With the number of OPERABLE Channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to initiate a rod block by the associated Trip Function, and place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, initiate a rod block.

i CLINTON - UNIT 1 3/4 3-65 Amendment No. 79

TABLE 3.3.6-2 CONTROL RCD BLOCK INSTRUMENTATION SETPOINTS U

TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE h

1.

R0D PATTERN CONTROL SYSTEM 7

a.

Low Power Setpoint 138.0 2.3 psig*

2 115.0 psig, s 175.0 psig*

b.

RWL High Power Setpoint s 361.6 psig*

s 400 psig*

e 2.

APRM a.

Flow Biased Neutron Flux

~

- Upscale

1) During two recirculation loop operation:

a)

Flow Biased s 0.66W + 58%** with a maximum s 0.66W + 61%** with a maximum of of b) High Flow Clamped s 108.0% of RATED THERMAL POWER s 110.0% of RATED THERMAL POWER

2) During single recirculation R[

loop operation:

a)

Flow Biased s 0.66(W-oW) + 42%**

s 0.66(W-oW) + 45%**

a b) High Flow Clamped Not required OPERABLE Not required OPERABLE b.

Inoperative NA NA c.

Downscale 2 5% of RATED THERMAL POWER 2 3% of RATED THERMAL POWER d.

Neutron Flux - Upscale Startup s 12% of RATED THERMAL POWER s 14% of RATED THERMAL POWER 3.

SOURCE RANGE MONITORS a.

Detector not full in NA NA 5

b.

Upscale s 1 x 10 cps s 1.6 x 10' cps c.

Inoperative NA NA d.

Downscale E

2 3 cps g

4.

INTERMEDIATE RANGE MONITORS 2 1.8 cps k

a.

Detector not full in NA NA g

b.

Upscale s 108/125 division of full scale s 110/125 division of full scale c.

Inoperative NA NA' f

d.

Downscale 2 5/125 division of full scale 2 3/125 division of full scale M

e TABLE 3.3.6-2 (Continued)

CONTROL R00 BLOCK INSTRUMENTATION SETPOINTS TABLE NOTATIONS These are turbine first stage pressure valves.

The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W). The trip setting of this function must be maintained in accordance with note (a) of Table 2.2.1-1.

Instrument zero is 758' 5" msl.

1. Instrument zero is 758' 4 1/2" msl.

i CLINTON - UNIT 1 3/4 3-67 Amendment No. 79

)

J'...

s TABLE 4.3.6-1

{

CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

o*

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E

TRIP FUNCTION CHECK TEST CALIBRATION (a)

SURVEILLANCE REQUIRED 1.

ROD PATTERN CONTROL SYSTEM

~

-a.

Low Power Setpoint NA S/Ucb>

Q R")

1, 2

~

b.

RWL High Power Setpoint NA S/U >

tb Q

R"3 1

2.

APRM a.

Flow Biased Neutron Flux -

i Upscale NA S/Ucb> 9 34 y

b.

Inoperative NA S/U(6),Q NA 1, 2, 5 c.. Downscale NA S/Ucb),Q SA 1

d.

Neutron Flux - Upscale, Startup NA S/Ucb>,A SA 5

w.

A 3.

SOURCE RANGE MONITORS a.

Detector not full in NA W

NA 2**,

5 b.

Upscale NA W

R 2**,

5 c.

Inoperative NA W

NA 2**,

5

.d.

. Downscale NA-W R

2**,

5 4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in NA W

NA 2, 5 b.

Upscale NA W

R 2, 5

.c.

Inoperative NA W

NA 2, 5 d.

Downscale NA W

R 2, 5 5.

SCRAM DISCHARGE VOLUME a.

Water Level-High S

Q R")

1, 2, 5*

yg'

.6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW l

7 a.

Upscale NA

~ S/U"'),Q -

SA 1

S.

7.

REACTOR MODE SWITCH z

a.

Shutdown Mode NA R

NA 3, 4 P

b.

Refuel Mode NA R

NA 5

2 u

.f-

..e

-= 4

,,-e

.,4.-

,d...

3 TABLE 4.3.6-1 (Continued)

CONTROL R0D BLOCK INSTRUMENTATION SURVEILLANCE RE0VIREMENTS TABLE NOTATIONS (a) -Neutron detectors may be excluded from CHANNEL CALIBRATION.

t (b) Within 7 days prior to startup.

(c) Deleted (d) Deleted (e) Deleted (f) Calibrate the analog trip module at least once per 92 days;

[

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

With IRMs on range 2 or below.

-E i

CLINTON - UNIT 1 3/4 3-69 Amendment No. 79 i

3 INSTRUMENTATION 3/4.3.7 MONITORING INSlRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7 1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE, with their alarm / trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3.7.1-1.

ACTION:

With a radiation monitoring instrumentation channel alarm / trip setpoint a.

exceeding the value shown en Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHt'NEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the l

c:nditier and at the frequencies shown in Table 4.3.7.1-1.

t CLINTON - UNIT 1 3/4 3-70 Amendment No.40

TABLE 4.3.7.5-1 52 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'i E

APPLICABLE CHANNEL CHANNEL OPERATIONAL c-INSTRUMENT CHECK CALIBRATION CONDITIONS l

Z 1.

Reactor Vessel Pressure M

R 1,2,3 2.

Reactor Vessel Water Level M

R 1,2,3 3.

Suppression Pool Water Level M

R 1,2,3 4.

Suppression Pool Water Temperature M

R 1,2,3 5.

Drywell Pressure M

R 1,2,3 6.

Drywell Air Temperature M

R 1,2,3 7.

Drywell/ Containment Hydrogen and Oxygen Concentration M*

g Analyzer and Monitor Q*

1,2,3

[

8.

Containment Pressure M

R 1,2,3 g

9.

Containment Temperature M

R 1,2,3 10.

Safety / Relief Valve Acoustic Monitor NA R

1,2,3 11.

Containment /Drywell High Range Gross Gamma Radiation M

R**

1,2,3 Monitors 12.

HVAC Stack High Range Radioactivity Monitor #

M R##

1,2,3 13.

SGTS Exhaust High Range Radioactivity Monitor #

M R##

1,2,3 14.

Primary Containment Isolation Valve Position M

Rt 1,2,3 Indication i,

Accomplished automatically using an integral sample gas supply containing 3.2 vol.% hydrogen, i

21 vol.% oxygen, 0.9 vol.% argon and 74.9 vol.% nitrogen.

- The CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/br and a one point calibration check of the detector below 10 R/hr with an installed or pnrtable gamma source.

High range noble gas monitor, and fodine/ particulate sampler.

1. Channel calibration is not required to be performed on iodine / particulate sampler.

tThe CHANNEL CALIBRATION should demonstrate that valve operation is accurately indicated.

'i INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

In OPERATIONAL CONDITION 2*, three.

a.

b.

In OPERATIONAL CONDITIONS 3 and 4, two.

APPLICABILITY:

OPERATIONAL CONDITIONS 2*, 3 and 4.

ACTION:

In OPERATIONAL CONDITION 2* with one of the above required source range a.

monitor channels inoperable, restore at least three source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable control rods to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within I hour.

SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the atJve required source range monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in OPERATIONAL CONDITION 2* and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 3 or 4.

2.

CHANNEL CALIBRATION" at least once per 18 months.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 or 3 from OPERATIONAL CONDITION I, provided the i

surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2 or 3.

P

With IRMs on range 2 or below.

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

CLINTON - UNIT I 3/4 3-90 Amendment No. 79

1 4

INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION (Continued) b.

Performance of a CHANNEL FUNCTIONAL TEST:

l.

Within 7 days prior to moving the reactor mode switch from the Shutdown position, and 2.

At least once per 31 days.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 or 3 from OPERATIONAL CONDITION 1, provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2 or 3.

c.

Verifying, prior {,o withdrawal of control rods, that the SRM count rate is at least 3 cps with the detector fully inserted.

With IRMs on range 2 or below.

- For the initial core loading, the count rate may be reduced to 0.7 cps provided signal to noise ratio is 220.

CLINTON - UNIT 1 3/4 3-90a Amendment No. 79

ML20046C169

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