RS-05-039, Response to Request for Additional Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values

Response to Request for Additional Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values

ML050890468
Person / Time
Site:	Clinton
Issue date:	03/30/2005
From:	Jury K AmerGen Energy Co, Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-05-039
Download: ML050890468 (41)

Text

Tation www.exeloncorp .com 4300' ) J WaTre-nville, I L 60555 RS-05-039 March 30, 2005 U . S . Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Response to Request for Additional Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values

References:

1 . Letter from Keith R. Jury (AmerGen Energy Company, LLC) to U. S .

Nuclear Regulatory Commission, "Request for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values," dated November 11, 2003

2. Letter from Kahtan N. Jabbour (U . S. Nuclear Regulatory Commission) to Christopher M . Crane (AmerGen Energy Company, LLC), "Clinton Power Station, Unit 1 - Request for Additional Information Re: Instrument Channel Trip Setpoint Allowable Values (TAC No. MC1 323)," dated March 11, 2005 In Reference 1, AmerGen Energy Company, LLC (AmerGen) submitted a request for a change to Appendix A, Technical Specifications (TS), of Facility Operating License No. NPF-62 for Clinton Power Station (CPS). Specifically, the proposed change requested revisions to instrument channel trip setpoint allowable values for thirteen TS defined functions. The current allowable values for these functions were determined to require revision during a detailed review of all CPS instrumentation setpoints and allowable values .

In Reference 2, the NRC requested additional information to complete the review of the license amendment. This request pertained to AmerGen's use of Instrument Society of America (ISA) recommended practice ISA-RP67.04-1994, Part 11, "Methodologies for Determination of Setpoints for Nuclear Safety-Related Instrumentation," Method 3, to establish the allowable values .

March 30, 2005 U. S . Nuclear Regulatory Commission Page 2 of this letter provides the requested information . As described in , AmerGen proposes to add a Note to the affected TS pages . provides revised markups for the affected TS pages. Attachment 3 provides retyped TS pages for both the changes proposed in Reference 1, and the additional changes proposed in this letter .

AmerGen has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment 1 of Reference 1 .

The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration .

There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Mr. Timothy A. Byarn at (630) 657-2804 .

I declare under penalty of perjury that the foregoing is true and correct . Executed on the 30th day of March 2005 .

Keith R. Jury Director, Licensing and Regulatory Affairs AmerGen Energy Company, LLC Attachments:

1 . Response to Request for Additional Information

2. Markup of Proposed Technical Specifications Pages 3 . Retyped Technical Specifications Pages

ATTACHMENT 1 Response to Request for Additional Information NRC Request .1 Discuss the setpoint methodology used at Clinton Unit 1 to establish AVs associated with LSSS setpoints.

Response

In Reference 1, AmerGen Energy Company, LLC (AmerGen) submitted a request for a change to Appendix A, Technical Specifications (TS), of Facility Operating License No. NPF-62 for Clinton Power Station (CPS). Specifically, the proposed change requested revisions to instrument channel trip setpoint allowable values for thirteen TS defined functions . The current allowable values for these functions were determined to require revision during a detailed review of all CPS instrumentation setpoints and allowable values .

The new allowable values proposed in Reference 1 were calculated in accordance with the guidance provided in NRC Regulatory Guide 1 .105, "Setpoints for Safety-Related Instrumentation," Revision 1, as implemented by the CPS Setpoint Methodology and the Instrument Society of America (ISA) Standard S67.04, "Setpoints for Nuclear Safety Related Instrumentation," dated September 1994.

Details regarding the setpoint methodology used at CPS to establish allowable values associated with limiting safety system settings (LSSSs) were provided to the NRC in Reference 2 . Specifically, in response to an NRC request, AmerGen submitted the CPS Setpoint Methodology (i .e., CI-01 .00, "Instrument Setpoint Calculation Methodology") along with several representative calculations that were performed using the methodology .

NRC Request 2 Regardless of the methodology used, the NRC staff has the following questions regarding the use of the methodology at Clinton Unit 1 :

a . Discuss how the methodology and controls you have in place ensure that the analytical limit associated with an LSSS trip setpoint will not be exceeded (that the safety limit will not be exceeded). Include in your discussion information on the controls you employ to ensure the trip setpoint established after completing periodic Ewrveillances satisfies your methodology.

If the controls are located in a document other than the TSs, discuss how those controls satisfy the requirements of 10 CFR 50.36.

b . Discuss how the TS surveillances ensure the operability of the instrument channel .

Specifically, relate the surveillance test results to the TS AVs and describe how these are used to determine the operability of the instrument channels . If the requirements for determining operability of the LSSS instrument being tested are in a document other than the TSs (e.g ., plant test procedures), discuss how this meets the requirements of 10 CFR 50.36.

ATTACHMENT 1 Response to Request for Additional Information

Response

Some of the instrument channel trip setpoint allowable values proposed in Reference 1 were established in accordance with ISA recommended practice ISA-RP67.04, Part 11, Method 3 .

The following table lists the allowable values that were calculated using this methodology .

TS Table Function Description _

3 .3.5.1-1 1 .a Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS) Subsystems - Reactor Vessel Water Level-Low Low 3.3.5.1-1 2 .a LPCI B and LPCI C Subsystems - Reactor Vessel Water Level-Low Low Low, Level 1 3.3.5.1-1 3.a High Pressure Core Spray (HPCS) System - Reactor Vessel Water I Level-Low Low, Level 2 HPCS System - Reactor Vessel Water Level-High, Level 8 3.3 .5 .1-1 4.a Automatic Depressurization System (ADS) Trip System 1 (Logic A and E) - Reactor Vessel Water Level-Low Low Low, Level 1 3 .3 .5.1-1 5.a ADS Trip System 2 (Logic B and F) - Reactor Vessel Water Level-Low Low Low, Level 1 3 .3.5.2-1 1 Reactor Core Isolation Cooling (RCIC) System - Reactor Vessel Water Level-Low Low, Level 2 3.3.6.1-1 1 .a Main Steam Line Isolation - Reactor Vessel Water Level-Low Low Low, Level 1 3.3.6.1-1 1 .b Main Steam Line Isolation - Main Steam Line Pressure-Low 3.3 .6.1-1 2.a Primary Containment and Drywell Isolation - Reactor Vessel Water Level-Low Low, Level 2 3.3.6.1-1 2.e Primary Containment and Drywell Isolation - Reactor Vessel Water Level-Low Low, Level 2 (HPCS NSPS Div 3 and 4) 3.3 .6.1-1 2.j Primary Containment and Drywell Isolation - Reactor Vessel Water Level-Low Low Low, Level 1 3.3 .6.1-1 3 .h RCIC System Isolation - Reactor Vessel Water Level-Low Low, Level 2 3.3.6.1-1 4.f Reactor Water Cleanup System Isolation - Reactor Vessel Water I Level-Low Low, Level 2 3.3.6.1-1 5 .d Residual Heat Removal (RHR) System Isolation - Reactor Vessel Water Level-Low Low Low, Level 1 3.3.6 .2-1 Secondary Containment Isolation - Reactor Vessel Water Level-Low Low, Level 2 3 .3.6.3-1 RHR Containment Spray System - Reactor Vessel Water Level-Low Low Low, Level 1 3 .3.6.4-1 Suppression Pool Makeup System - Reactor Vessel Water Level-Low Low Low, Level 1

ATTACHMENT 1 Response to Request for Additional Information AmerGen encourages the NRC to work closely with the Nuclear Energy Institute while formulating any generic recommendations on this subject . Until a final resolution is reached, AmerGen will modify the TS associated with the functions listed above to add a Note regarding as-left trip setpoints for the specified instruments. This Note states :

"This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint ."

The addition of this Note was previously discussed with the NRC on January 10, 2005, in a teleconference related to a request for license amendment for Quad Cities Nuclear Power Station, Units 1 and 2, and subsequently documented in Reference 3 . Adjustment of the trip setpoint to within the established setting tolerance ensures that the analytical limit, and therefore the safety limit, will not be exceeded . The addition of this Note for CPS was also discussed during the January 10, 2005, teleconference and provides an alternative approach that provides adequate confidence that the plant will operate in accordance with the safety analyses and shows that operability is ensured in the TS .

References 1 Letter from Keith R. Jury (AmerGen Energy Company, LLC) to U. S . Nuclear Regulatory Commission, "Request for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values," dated November 11, 2003

2. Letter from Keith R. Jury (AmerGen Energy Company, LLC) to U . S. Nuclear Regulatory Commission, "Response to Request for Supporting Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values," dated April 16, 2004

3. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U . S. Nuclear Regulatory Commission, "Additional Information Supporting Main Steam Line Flow - High Instrumentation Amendment Request," dated January 21, 2005

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages CLINTON POWER STATION FACILITY OPERATING LICENSE NO. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 3.3-39 3.3-40 3 .3-41 3 .3-42 3 .3-43 3 .3-47 3 .3-55 3 .3-56 3 .3-57 3 .3-58 3 .3-59 3.3-60 3.3-64 3.3-68 3.3-72

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3,5 .1-1 (page I of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 1 . Low Pressure Coolant Injection-A (LPC& and Low Pressure Core Spray (LPCS)

Subsystems a . Reactor Vessel Water 1,2,3, SR 3 .3 .5 .1 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 Level 1 4 0), 5(a) SR 3 .3 .5 .1 .3 SR 3,3 .5 .1 .4 SR 3 .3 .5 .1 .5 b, Drywall Pressure-High 1,2,3 2 (b) SR 3 .3 .5 .1 .1 1 1 .88 psig SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . LPCI Pump A 1,2,3, 1 C SR 3 .3 .5 .1 .2 > 4 .5 seconds Start-Time Delay SR 3 .3 .5 .1-4 and Logic Card ~a) 5 (a) SR 3 .3 .5 .1 .5 5 5 .5 seconds d . Reactor Vessel 1,20 C SR 3 .3 .5 .1 .1 Pressure-Low SR 3,3 .5 .1 .2 (Injection Permissive) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1,4 SR 3 .3 .5 .1 .5

'5 0) e . LPCS Pump Discharge SR 30 .5 .1 .1 A 750 gpm Flow-Low (Bypass) SR 3 .3 .5 .10 SR 3 .3 .5 .1 .3 SR 3,3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . LPCI Pump A Discharge 1,2,3, SR 3 .3 .5 .1 .1 11 goo gpm Flow-Low (Bypass) SR 3 .3 .5 .1 .2

( .1 ,501 SR 3 .3 .5 .1 .3 SR 3,3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . Manual initiat 1,20, SR 3,3 .5 .1 .5 NA

,5 ' a)

(continued)

(a) When associated subsystem(s) are required to be OPERABLE .

(b) Also required to initiate the associated diesel generator .

CLINTON 3 .3-39 Amendment No . 45y98

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3 .5 .1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE z LPCI B and LPCI C Subsystems a . Reactor Vessel Water 1,2,3, 8 SR 3 .3-5 .1 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 Level 1 SR 3 .3 .5 .2 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell Pressure-High 1,2,3 2`°' B SR 3 .3 .5 .1 .1 < 2 .88 psig SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3,3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . LPCI Pump B 1,2,3, 1 C SR 3 .3 .5 .1 .2 z 4 .5 seconds start-Time Delay SR 3 .3 .5 .1 .4 and Logic Card 4 (a), 54a) SR 3 .3 .5 .1 .5 A 5 .5 seconds d . Reactor vessel 1,2,3 4 C SR 3 .3-5 .1 .2 Pressure-Low SR 3 .3 .5 .1 .2 (Injection Permissive) SR 3 .3-5 .1 .3 SR 3,3 .5 .1 .4 3 .3 .5 .1, 4 (a) 5 SR 3 .3 .5 .1 .1 Z (452)-ps i g 4)

SR 3 . 3-5-1 . 2 an 3 . . 5 . 13

. - A- I S ,

SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCI Pump B and LPCI 1,2,3, 1 per pump E SR 3 .3 .5 .1 .1 > goo gpm Pump C Discharge SR 3 .3 .5 .1 .2 Flow-Low (Bypass) 4{a),51") SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . Manual Initiation 1,2,3, 1 C SR 3 .3 .5 .1 .5 NA 0)

Is (continued)

(a) When associated subsystem (s) are required to be OPERABLE .

(b) Also required to iota the associated diesel generator .

CLINTON 3 .3- 4 0 Amendment No . 45798

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3 .5 .1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 3 . High Pressure Core Spray (HPCS) System a . Reactor Vessel Water 1,2,3, 4 B SR 3 .3 .5 .1 .1 Level-Low Low, Level 2 SR 3,3 .5 .1 .2 (a) 3 .3 .5 .1 .3 SR SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 1,20 SR 3 .3 .5 .1 .1 SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .30 .1 .4 SR 3 .3 .5 .1 .5 c . Reactor Vessel Water 2 C SR 3 .3 .5 .1 .1 Level-High, SR 30 .5 .1 .2 Level 8 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 d . RCIC Storage Tank Level- 1,23, 2 D SR 3 .3 .5 .1 .1 Low SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . Suppression Pool Water 1,2,3 2 1) SR 3 .3 .5 .1 .1 Level-High SR 3 .3 .5 .1 .2 SR 30 .5 .1 .3 SR 30 .5 .1 .4 SR 3 .3 .5 .1 .5 f . HPCS Pump 1,20, 1 E SR 3 .3 .5 .1 .1 1. 120 ps i g Discharge SR 3 .3 .5 .1 .2 Pressure-High (Bypass) 45t,5" SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . HPCS System Flow Rate- 1,2,3, E SR 3 .3 .5 .1 .1 2! 500 gp, Low (Bypass) SR 3 .3 .5 .1 .2 4 0i , 5 0) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .30 .1 .5 h- Manual Initiation 1,2,3, 1 C SR 3 .3 .5 .1 .5 NA (continued)

(a) When associated subsystem(s) are required to be OPERABLE .

(b) Also required to initiate the associated diesel generator, (c) When HPCS is OPERABLE for compliance with LCO 3 .5 .2, "ECCS-Shutdown, " and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3 .50-2 .

CLINTON 3 .3- 4 1 Amendment No . 104

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3 .5 .1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE 4 . Automatic Depressurization System (ADS) Trip System I (Logic A and E) a . Reactor Vessel Water 1, 2 W), 3 No 2 SR 3 .3 .5 .1 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 Level 1 SR 3 .3 .5-1 .3 SR 3 .3-5 .1,4 SR 3 .3 .5 .1 .5 2 b . Drywall 1,2",3 W) F SR 3 .3 .5,1 .1 5 1 .86 prig Pressure-High SR 3 .3 .5 .1 .2 SR 3,3 .5-1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . ADS Initiation Timer 1, 2 to, 3 to SR 3 .3 .5-1 .2 1 117 seconds SR 3 .3 .5 .1 .4 SR 3 .3 .5-1 .5 d . Reactor Vessel Water '2 to, 3 (w SR 3 .3-5 .1 .1 Level-Low, Level 3 SR 3 .3 .5 .1 .2 (Confirmatory) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCS Pump Discharge 1,2 Is , 30) 2 G SR 3 .3 .5 .1 .1 Pressure-High SR 3 .3 .5 .1 .2 SR 3,3 .5 .1 .3 SR YY5 .1,4 SR 3 .3 .5 .1 .5 f . LPCI Pump A 1, 2 IN, 3 to SR 3 .3 .5 .1 .1 Discharge Pressure- SR 3 .3 .5 .1 .2 High SR 3 .3 .5 .1 .3 SR 30 .5 .1 .4 SR 3 .3 .5 .1 .5 2 g . ADS Drywall Pressure 1,243 46 G SR 3 .3 .5 .1 .2 Bypass Timer SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 h . Manual Initiation 1,2 to, 3 W) 2 G SR 3 .3 .5 .1 .5 NA (continued)

(d) With reactor steam dome pressure > 150 prig .

CLINTON 3 .3- 4 2 Amendment No . 95

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3 .5 .1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE

5. ADS Trip System 2 (Logic B and F)

, 3 to a, Reactor Vessel Water 1,2 to SR 3 .3 .5 .1 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 Level 1 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .10 Y Drywell Pressure-High 1,2 (0, 3 to SR 3 .3 .5 .1 .1 _< 1 .88 prig SR 3 .3 .5-1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . ADS Initiation Timer 1,2 to, 3 to G SR 3 .3 .5 .1 .2 :5 117 seconds SR 3 .30 .1-4 SR 3 .3 .5 .1 .5 d . Reactor Vessel Water 1,2(0,3 1d) SR 3 .3 .5 .1 .1 > 8 .3 inches Level-Low, Level 3 SR 3 .3 .5 .1 .2 (Confirmatory) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1-5 e . LPCI Pumps B & C 1,2 (d) 13 to 2 per pump G SR 3 .3 .5 .1 .1 Discharge SR 3 .3 .5 .1 .2 Pressure-High SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . ADS Drywell Pressure 1&a},3(a) 2 G SR 3 .3 .5 .1 .2 Bypass Timer SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 yn Manual Initiation 1, 2's, 3 (d) G SP 3 .3 .5 .1 .5 NA (d) With reactor steam dome pressure > 150 psig .

CLINTON 3 .3- 4 3 Amendment No . 95

RCIC System Instrumentation 3 .3 .5 .2 Table 3 .3 .5 .2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED FROM CHANNELS PER REQUIRED ACTION SURVEILLANCE ALLOWABLE FUNCTION FUNCTION A .1 REQUIREMENTS VALUE 1 . Reactor Vessel Water 4 B SR 3 .3 .5 .2 .1 Level-Low LOW, Level 2 SR 3 .3 .5-2-2 SR 3,3 .5 .2 .3 SR 3 .3 .5 .2 .4 SR 3 .3 .5 .2 .5 2, Reactor Vessel Water 2 C SR 3 .3 .5 .2 .1 Level-High, Level 8 SR 3 .3 .5 .2 .2 SR Y3 .5 .2-3 SR 3 .3 .5 .2 .4 SR 3,3 .5 .2 .5

3. RCIC Storage Tank 2 D SR 3 .3 .5 .2 .1 Level-Low SR 3 .3 .5 .2 .2 SR 3 .3 .5 .2 .3 SR 3 .3 .5 .2 .4 SR 3 .3 .5 .2 .5

4. Suppression Pool Water 2 D SR 3 .3 .5 .2 .1 Level-High SR 3 .3 .5 .2 .2 SR 3 .3 .5 .2 .3 SR 3 .3-5 .2-4 SR 3 .3 .5 .2 .5

. Manual Initiation I C SR 3 .3 .5 .2 .5 NA CLINTON 3 .3-47 Amendment No . 104

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 1 of 6)

Primary Containment and Drywall Isolation Instrumentation CABL CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS Main Steam Line Isolation a . Reactor Vessel Water 1,2,3 4 G SR 3 .3 .6 .1 .1 Level-Low Low Low, SR 3 .3 .6 .1 .2 Level I SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 b . Main Steam Line 4 H SR 3 .3 .6 .1 .1 Pressure-Low SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 c . Main Steam Line 1,2,3 4 G SR 3 .3 .6 .1 .1 Flow-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 d . Condenser Vacuum-Low 1,0 4 , 4 G SR 3 .3 .6 .1 .1 1 7 .6 inches SR 3 .3 .6 .1 .2 Hg vacuum 3 0) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e, main Steam Tunnel 1,2,3 4 G SR 3 .3 .6 .1 .1 Y 171 - F Temperature-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Main Steam Line Turbine 1,2,3 4 G SR 3 .3 .6 .1 .1 Modules 1-4 Building SR 3 .3 .6 .1 .2 1 142 0 F, Temperature-High SR 3 .3 .6 .1 .5 Module 5 SR 3 .3 .6 .1 .6 5 150 , E g . Manual Initiation 1,2,3 4 j SR 3 .3 .6 .1 .6 NA CLINTON 3 .3-55 Amendment No . 249

y Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 2 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM PER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE Primary Containment and Drywell isolation a . Reactor Vessel Water 1,2,3 4 (b) K SR 3 .3 .6 .1 .1 Level-Low Low, Level 2 SR 3 .3 .6 .1 .2 SR 3 .3-6 .1 .3 SR 30,6 .1 .5 SR 3 .3 .6 .1 .6 4 0 SR 3,3 .6 .1 .1 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 b, Drywell Pressure-High 1,2,3 4 K SR 3 .3 .6 .1 .1 SR 3 .3 .6 .1 .2 SR 3 .3 .6,10 SR 3 .3 .6 .1,5 SR 3 .3 .6 .1 .6 c . Deleted d . Drywell Pressure-High 1,2,3 4 (b) SR 3 .3 .6 .1 .1 (ECCS Divisions I SR 3 .3 .6 .1 .2 and 2) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Reactor Vessel Water 1,2,3 4 1 SR 3 .3 .6 .1 .1 Level-Low Low, Level SR 3 .3 .6-1 .2 2 (HPCS NSPS Div 3 SR 3 .3 .6 .1 .3 and 4) SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Drywell Pressure-High 1,2,3 4 1 SR 3 .3 .6 .1 .1 1 1 .88 psig (HPCS NSPS Div 3 and SR 3 .3 .6 .1 .2

4) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (continued)

(b) Also required to initiate the associated drywell isolation function .

(a During operas with a potential for draining the reactor vessel, CLINTON 3 .3- 5G Amendment No . 152

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 3 of 6)

Primary Containment and Dryvell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE

2. Containment and Isolation Wk W) SR 3 .3 .6 .1 .1 9 . Containment Building A 500 mR/hr Fuel Transfer Pool SR 3 .3 .6 .1 .2 Ventilation Plenum SR 3 .3 .6 .1 .5 Radiation-High SR 3 .3 .6 .1 .6 h . Containment Building 1,2,3 4 1 SR 3 .3 .6 .1 .1 5 400 mR/hr Exhaust SR 3 .3 .6 .1 .2 Radiation-High SR 3 .3 .6 .1 .5 SR 3 .3 .6-1 .6 (CA I fo 4 N SR 3 .3 .6 .1 .1 ! 400 mR/hr SR 3 .3 .6 .1 .2 SR 3 .3 .6 .10 SR 3 .3 .6 .1 .6 Containment Building 1,23 4 1 SR 304 .1 .1 A 400 mR/hr Continuous Containment SR 3 .34 .10 Purge (CCP) Exhaust SR 3 .3 .6 .1 .5 Radiation-High SR 3 .3 .6 .1 .6 (ei, ld) SR 3 .3 .6 .1 .1 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 j . Reactor Vessel Water 1,2,3 4 ib) SR 3 .3 .6,1 .1 Level-Low Low Low, SR 3 .3 .6,1 .2 Level I SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1-6 lei 4 0 SR 3 .3 .6,1 .1 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 k . Containment Pressure- 2 1 SR 3 .3 .6 .1 .1 5 3 .0 psid High SR 30 .6 .1 .2 SR 3 .3 .6 .1-5 SR 3 .3 .6 .1 .6 1 . Manual Initiation 1,2,3 Q) i SR 3 .3 .6 .1 .6 AA 1c) . (d) 14 SR 3 .3,6 .1 .6 NA (continued)

(b) Also required to initiate the associated drywell isolation function .

(c) During operations with a potential for draining the reactor vessel .

Q During movement of recently irradiated fuel assemblies in the primary or secondary containment .

and 3 with the associated PCIVs not closed_

CLINTON 3 .3-57 Amendment No . 147

Primary Containment and Drywall Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 4 of 6)

Primary Containment and Drywall Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE 3 . Reactor Core Isolation Cooling (RCIC) System Isolation a, Auxiliary Building 1,2,3 2 SR 3 .3 .6 .1 .1 i 118 .5 inches RCIC Steam Line SR 3 .3 .6 .1 .2 water Flow-High SR 3 .3 .6 .1 .3 SR 3 .34 .1 .5 SR 3 .3 .6 .1 .6 b . RCIC Steam Line 1,2,3 2 1 SR 3 .3 .6 .1 .2 i 13 seconds Flow-High, SR 3 .3 .6 .1 .5 Time Delay SR 3 .3 .6 .1 .6 C . RCIC Steam Supply Line 1,2,3 2 1 SR 3 .3 .6 .1 .1 A 52 psig Pressure-Low SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6-1 .6 d . RCIC Turbine Exhaust 1,2,3 4 1 SR 3 .3 .6 .1 .1 S 20 psig Diaphragm SR 3 .3 .6 .1 .2 Pressure-High SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3,3 .6 .1 .6 e . RCIC Equipment Room 1,2,3 2 1 SR 3 .3 .6 .1 .1 5 207'F Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Main Steam Line Tunnel 1,2,3 2 1 SR 3 .3 .6 .1 .1 5 171'F Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 Line Tunnel 1,2,3 2 SR 3,3 .6 .1 .2 1 28 minutes 9.

Timer SR 3 .3 .6 .1 .5 SR 3 .35 .1 .6 h, Reactor Vessel water 1,2,3 4 1 SR 3 .3 .6 .1 .1 Level-Low Low, Level 2 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 Drywall RCIC Steam 1,2,3 2 1 SR 30 .6 .1 .1 5 198 inches Line Flow - High SR 3 .3 .6 .1 .2 water SR 3 .3 .6 .1 .3 SR 3 .3 .6-1 .5 SR 3 .3 .6 .1 .6 (continued)

CLINTON 3 .3- 5 8 Amendment No . 152

Primary Containment and Drywall Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 5 of 6)

Primary Containment and Drywall Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE VALUE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS

3. RCIC system isolation (continued)

Pressure - High 1,2 .3 2 SR 3 .3 .6 .1 .1 A 1 .88 psig SR 3 .3 .6 .1 .2 SR 30 .01 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 k . Manual Initiation 1,20 1 1 SR 3,3 .6 .1 .6 NA Reactor Water Cleanup (RWCU) System isolation a, Differential Flow - 1,20 2 1 SR 3 .3 .&I .l 5 66 .1 gpM High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1,5 SR 3 .3 .6-1 .6 b . Differential Flow-Timer 1,20 2 1 SR 3 .3 .6 .1 .2 1 47 seconds SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .6 C . RWCU Heat Exchanger 1,2,3 2 per I SR 3 .3 .6 .1 .1 A 205OF Equipment Room room SR 3 .3 .6 .1 .2 Temperature-High SR 3,3 .6 .1 .5 SR 3 .3 .6 .1 .6 d . RWCU Pump ROOMS 1,20 2 per I SR 3 .3 .6 .1 .1 Y 202-F Temperature-High room SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6

e. Steam Line Tunnel 1,2,3 SR 3 .3 .6 .1 .1 1 171 - F ant Temperature- SR 3 .3 .6 .10 SR 30 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Reactor Vessel Water 1,2,3 4 1 SR 3 .3 .6 .1 .1 Level-Low Low, SR 3 .3 .6 .1 .2 Level 2 SR 3 .3 .6 .1 .3 SR 3 .3 .01 .5 SR 3 .3 .6 .1 .6 SR 30 .6 .1 .1 SR 3 .3 .6 .1 .2 SR 3 .3 .01 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 g, Standby Liquid Control 1,2 2 L SR 3 .3 .6 .1 .6 NA System Initiation h . Manual initiation 1,2,3 2 j SR 3 .3 .6 .1 .6 NA (c), (d) 2 N SR 3 .3 .6 .1 .6 NA (continued)

(c) During operations with a potential for draining the reactor vessel .

(d) During movement of recently irradiated fuel assemblies in the primary or secondary containment .

CLINTON 3 .3- 5 9 Amendment No . 152

Primary Containment and Drywall Isolation Instrumentation 3 .3 .6 .1 ITable 3 .3 .6 .1-1 (page 6 of 6)

Primary Containment and Drywall Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE S . RHR System isolation a . RHR Heat Exchanger 1,2,3 2 per room I SR 3 .3 .6 .1 .1 , 160-F Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 4 b . Reactor Vessel Water 1,2,3" 1 1 SR 3 .3 .6 .1 .1 A 8 .3 inches Level - Low, Level 3 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3-6 .1 .5 SR 3 .3 .6 .1 .6 4(W c, Reactor vessel water 3'W,4,5 M SR 3 .3 .6 .1 .1 Level - Low, Level 3 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 d, Reactor vessel water 1,2,3 4 1 SR 3 .3 .6 .1 .1 Level - Low Low Low, SR 3 .3 .6 .1 .2 Level I SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Reactor vessel 1,2,3 4 1 SR 3 .3 .6,1 .1 A 110 psig Pressure-High SR 30 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Drywall Pressure-High 1,2,3 8 1 SR 3 .3 .6 .1 .1 A 1 .88 psig SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 g, Manual initiation 1,2,3 2 j SR 3 .3 .6 .1 .6 NA with reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure .

with reactor steam dome pressure less than the RHR cut in permissive pressure .

Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained .

CLINTON 3 .3- 6 0 endment No . 104

Secondary Containment Isolation Instrumentation 3 .3 .6 .2 Table 3 .3 .6 .2-1 (page I of i)

Secondary Containment Isolation Instrumentation MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION __CONDITIONS SYSTEM REQUIREMENTS VALUE Reactor Vessel Water 1,2,3,(a) 2 SR 3 .3 .6 .2 .1 Level-Low Low, Level 2 SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .3 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5 Drywell Pressure-High 1,2,3 2 SR 3,3 .6 .2 .1 SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .3 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2,5 Containment Building Fuel (a) , (b) 2 SR 3 .3 .6 .2 .1 A 500 mR/hr Transfer Pool Ventilation SR 3 .3 .6 .2 .2 Plenum Exhaust SR 3 .3 .6 .2 .4 Radiation-High SR 3 .3 .6_2 .5 4, Containment Building 1,2,3, 2 SR 3 .3 .6 .2 .1 A 400 mR/hr Exhaust Radiation-High (a),(b) SR 3,3 .6 .2 .2 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5 5, Containment Building 1,2,3, 2 SR 3 .3 .6 .2 .1 i 400 MR/hr Continuous Containment (a),(b) SR 3 .3 .6 .2 .2 Purge (CCP) Exhaust SR 3 .3 .6 .2 .4 Radiation-High SR 3 .3 .6 .2 .5 Fuel Building Exhaust 1,2,3, 2 SR 3 .3 .6 .2 .1 S 17 mR/hr Radiation-High (c) SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5

7. manual initiation 1,2,3, 1 SR 3 .3 .6 .2 .5 NA (a) During operations with a potential for draining the reactor vessel, (b) Dur movement of recently irradiated fuel assemblies in the pr or secondary containment .

(c) During movement of recently irradiated fuel assemblies in the fuel building .

CLINTON 3 .3-64 Amendment No . 147

RHR Containment Spray System Instrumentation 3 .3 .6 .3 Table 3 .3 .6 .3-1 (page I of 1)

RHR Containment Spray System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION SYSTEM ACTION A .

1. Drywell Pressure-High 2 B SR 3 .3 .6 .3 .1 A 1 .88 psig SR 3 .3 .6 .3 .2 SR 3 .3-6 .3 .3 SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5 Conta Pressure-High 2 SR 3 .3 .6 .3 .1 SR 3 .3 .6 .3 .2 SR 3 .3 .6 .3 .3 SR 3-3 .6 .3 .4 SR 3 .3 .60 .5 Reactor Vessel Water 2 B SR 3 .3 .6 .3 .1 Level-Low Low Low, SR 3 .3 .6 .3 .2 Level 1 SR 3 .3,6 .3 .3 SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5 Timers, System A C SR 3 .3 .6 .3 .2 1 10 .10 minutes and and System B SR 3 .3 .6 .3 .4 A 10 .23 minutes SR 3 .3 .6 .3 .5 S. Timer, System B Only C SR 3 .3 .6 .3 .2 90 .6 seconds SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5 Manual initiation I C SR 3 .3 .6,3 .5 NA CLINTON 3 .3-68 Amendment No . 95

SPMU System Instrumentation 3 .3 .6 .4 Table 3 .3 .6 .4-1 (page 1 of 1)

Suppression Pool Makeup System Instrumentation REQUIRED CONDITIONS CHANNELS REFERENCED PER FROM TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION SYSTEM ACTION A . l_- R UIREMEN S VALUE-1, Drywell Pressure-High 2 B SR 3 .3 .6 .4 .1 S 1 .88 psig SR 3 .3 .6 .4 .2 SR 3 .3 .6 .4 .3 SR 3 .3 .6 .4-6 SR 3 .3 .6 .4 .7

2. Reactor Vessel Water 2 B SR 3 .3 .04 .1 Level-Low Low Low, SR 3 .3 .6 .4 .2 Level I SR 3,3 .6 .4 .3 SR 3 .3 .6 .4 .6 SR 3 .3 .6 .4 .7

3. Suppression Pool Water 2 B SR 3 .3 .6 .4 .1 A 29 inches Level-Low Low SR 3 .3-6 .40 SR 3 .3 .6 .4 .4 SR 3 .3 .6 .4 .6 SR 3 .3-6 .4 .7 Timer I C SR 3 .3 .6 .40 A 30 minutes SR 3 .3 .6 .4 .5 SR 3 .3 .04 .7

5. Manual Initiation 2 C SR 3 .3 .6 .4 .7 NA CLINTON 3 .3-72 Amendment No . 95

INSERT This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

ATTACHMENT 3 Retyped Technical Specifications Pages CLINTON POWER STATION FACILITY OPERATING LICENSE NO. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 3 .3-8 3.3-29 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-47 3.3-55 3.3-56 3.3-57 3.3-58 3.3-59 3.3-60 3.3-64 3.3-68 3.3-72 3.3-74

RPS Instrumentation 3 .3 .1 .1 Table 3 .3 .1 .1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION D .1 REQUIREMENTS VALUE

3. Reactor Vessel Steam Dome 1,2 4 H SR 3 .3 .1 .1 .1 5 1080 psig Pressure - High SR 3 .3 .1 .1 .9 SR 3 .3 .1 .1 .10 SR 3 .3 .1 .1 .13 SR 3 .3 .1 .1 .15 SR 3 .3 .1 .1 .17

4. Reactor Vessel Water 1,2 4 H SR 3 .3 .1 .1 .1 A 8 .3 inches Level-Low, Level 3 SR 3 .3 .1 .1 .9 SR 3 .3 .1 .1 .10 SR 3 .3 .1 .1 .13 SR 3 .3 .1 .1 .15 SR 3 .3 .1 .1 .17

5. Reactor Vessel Water A 21 .6 % RTP 4 F SR 3 .3 .1 .1 .1 i 52 .6 inches Level-High, Level 8 SR 3 .3 .1 .1 .9 SR 3 .3 .1 .1 .10 SR 3 .3 .1 .1 .13 SR 3 .3 .1 .1 .15 SR 3 .3 .1 .1 .17 Main Steam Isolation 1 4 G SR 3 .3 .1 .1 .9 5 13% closed Valve-Closure SR 3 .3 .1 .1 .13 SR 3 .3 .1 .1 .15 SR 3 .3 .1 .1 .17 Drywell Pressure-High 1,2 4 H SR 3 .3 .1 .1 .1 1 1 .88 psig SR 3 .3 .1 .1 .9 SR 3 .3 .1 .1 .10 SR 3 .3 .1 .1 .13 SR 3 .3 .1 .1 .15

8. Scram Discharge Volume Water Level-High

a. Transmitter 1,2 4 H SR 3 .3 .1 .1 .1 1 40-1/4 inches SR 3 .3 .1 .1 .9 for 1C11-SR 3 .3 .1 .1 .10 N601A,B and SR 3 .3 .1 .1 .13 5 39-3/16 SR 3 .3 .1 .1 .15 inches for 1C11-N601C,D 5W 4 SR 3 .3 .1 .1 .1 i 40-1/4 inches SR 3 .3 .1 .1 .9 for 1C11-SR 3 .3 .1 .1 .10 N601A,B and SR 3 .3 .1 .1 .13 i 39-3/16 SR 3 .3 .1 .1 .15 inches for 1C11-N601C,D (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies .

CLINTON 3 .3-8 Amendment No .

ATWS-RPT Instrumentation 3 .3 .4 .2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C .1 Remove the associated 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated recirculation pump from Completion Time not service .

met .

OR C .2 Be in MODE 2 . 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3 .3 .4 .2 .1 Perform CHANNEL CHECK . 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3 .3 .4 .2 .2 Perform CHANNEL FUNCTIONAL TEST . 92 days SR 3 .3 .4 .2 .3 Calibrate the trip units . 92 days SR 3 .3 .4 .2 .4 Perform CHANNEL CALIBRATION . The 18 months Allowable Values shall be :

a. Reactor Vessel Water Level-Low Low, Level 2 : A -50 .0 inches ; and

b. Reactor Steam Dome Pressure-High :

5 1143 psig .

SR 3 .3 .4 .2 .5 Perform LOGIC SYSTEM FUNCTIONAL TEST, 18 months including breaker actuation .

CLINTON 3 .3-29 Amendment No .

ECCS Instrumentation 3 .3 .5 .1 Table 3 .3 .5 .1-1 (page I of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE 1 . Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems a . Reactor Vessel Water 1,2,3, 2 (b) SR 3 .3 .5 .1 .1 ~! -148 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 inches (e) a) , 5(a)

Level 1 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell Pressure-High 1,2,3 2= B SR 3 .3 .5 .1 .1 5 1 .88 psig SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . LPCI Pump A 1,2,3, C SR 3 .3 .5 .1 .2 ~! 4 .5 seconds Start-Time Delay SR 3 .3 .5 .1 .4 and 4 (a) , S(a)

Logic Card SR 3 .3 .5 .1 .5 A 5 .5 seconds d . Reactor Vessel 1,2,3 C SR 3 .3 .5 .1 .1  ? 454 psig Pressure-Low SR 3 .3 .5 .1 .2 and (Injection Permissive) SR 3 .3 .5 .1 .3 <_ 494 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 4 on 5 (a) 4 B SR 3 .3 .5 .1 .1 A 454 psig SR 3 .3 .5 .1 .2 and SR 3 .3 .5 .1 .3 S 494 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCS Pump Discharge 1,2,3, SR 3 .3 .5 .1 .1 ~! 750 gpm Flow-Low (Bypass) SR 3 .3 .5 .1 .2 W , (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . LPCI Pump A Discharge 1,2,3, SR 3 .3 .5 .1 .1 A 900 9pm Flow-Low (Bypass) SR 3 .3 .5 .1 .2 (0 ,5 0) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . Manual Initiation 1,2,3, 1 C SR 3 .3 .5 .1 .5 NA 0 ,5 0)

(continued)

(a) When associated subsystem s) are required to be OPERABLE .

(b) Also required to initiate the associated diesel generator .

(e) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-39 Amendment No .

ECCS Instrumentation 3 .3 .5 . 1 Table 3 .3 .5 .1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE

2. LPCI B and LPCI C Subsystems a . Reactor Vessel Water 1,2,3, 2W SR 3 .3 .5 .1 .1 ~! -148 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 inches (e)

Level 1 4 W, 5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell Pressure-High 1,2,3 2 (b) SR 3 .3 .5 .1 .1 <_ 1 .88 psig SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5

c. LPCI Pump B 1,2,3, 1 C SR 3 .3 .5 .1 .2 ~! 4 .5 seconds Start-Time Delay SR 3 .3 .5 .1 .4 and 4 (a) ,5 (a)

Logic Card SR 3 .3 .5 .1 .5 :5 5 .5 seconds d . Reactor Vessel 1,2,3 4 C SR 3 .3 .5 .1 .1 A 454 psig Pressure-Low SR 3 .3 .5 .1 .2 and (Injection Permissive) SR 3 .3 .5 .1 .3 !~- 494 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 SR 3 .3 .5 .1 .1 A 454 psig SR 3 .3 .5 .1 .2 and SR 3 .3 .5 .1 .3 <_ 494 ps SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCI Pump B and LPCI 1,2, 3, 1 per pump E SR 3 .3 .5 .1 .1 ~! goo gpm Pump C Discharge SR 3 .3 .5 .1 .2 Flow-Low (Bypass) 4 (a) ,5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . Manual Initiation 1,2,3, 1 C SR 3 .3 .5 .1 .5 NA W, 5 (a)

(continued)

(a) When associated subsystem (s) are required to be OPERABLE .

W Also required to initiate the associated diesel generator .

(e) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-40 Amendment No .

ECCS Instrumentation 3 .3 .5 . 1 Table 3 .3 .5 .1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE 3 . High Pressure Core Spray (HPCS) System a . Reactor Vessel Water 1,2,3, 4 B SR 3 .3 .5 .1 .1 A -48 .1 Level-Low Low, Level 2 SR 3 .3 .5 .1 .2 inches (e) 4 W, 5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell 1,2,3 4 B SR 3 .3 .5 .1 .1 5 1 .88 psig Pressure - High SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . Reactor Vessel Water 1,2,3, 2 C SR 3 .3 .5 .1 .1 1 54 .6 Level-High, SR 3 .3 .5 .1 .2 inches (e)

Level 8 4 5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 d . RCIC Storage Tank Level- 1,2,3, 2 D SR 3 .3 .5 .1 .1 A 3 .0 inches Low SR 3 .3 .5 .1 .2 4 W, 5 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . Suppression Pool Water 1,2,3 2 D SR 3 .3 .5 .1 .1 0 11 inches Level-High SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . HPCS Pump 1,2,3, 1 E SR 3 .3 .5 .1 .1 1 120 psig Discharge SR 3 .3 .5 .1 .2 Pressure-High (Bypass) 1 (a) ,5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . HPCS System Flow Rate- 1,2,3, 1 E SR 3 .3 .5 .1 .1 t 500 gpm Low (Bypass) SR 3 .3 .5 .1 .2 4w, 5 (a) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 h . Manual Initiation 1,2,3, 1 C SR 3 .3 .5 .1 .5 NA a) (a)

(continued)

(a) When associated subsystem s) are required to be OPERABLE .

(b) Also required to initiate the associated diesel generator .

(c) When HPCS is OPERABLE for compliance with LCO 3 .5 .2, "ECCS-Shutdown," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3 .5 .2 .2 .

(e) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-41 Amendment No .

ECCS Instrumentation 3 .3 .5 . 1 Table 3 .3 .5 .1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE REQUIREMENTS FUNCTION CONDITIONS FUNCTION ACTION A ." VALUE 4 . Automatic Depressurization System (ADS) Trip System 1 (Logic A and E) a . Reactor Vessel Water 1,2c6,3(a) SR 3 .3 .5 .1 .1 -148 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 inches tee Level 1 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell 1,2W 3 0) 2 F SR 3 .3 .5 .1 .1 5 1 .88 psig Pressure-High SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 C . ADS Initiation Timer ,2(0,3 (d) G SR 3 .3 .5 .1 .2 <_ 117 seconds SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 d . Reactor Vessel Water 2 (M , 3 (d) SR 3 .3 .5 .1 .1 ~! 8 .3 inches Level-Low, Level 3 SR 3 .3 .5 .1 .2 (Confirmatory) SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCS Pump Discharge 1,2 (y NT 2 G SR 3 .3 .5 .1 .1 ~! 125 psig Pressure-High SR 3 .3 .5 .1 .2 and SR 3 .3 .5 .1 .3 A 176 .3 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 W

f . LPCI Pump A ,2 130) 2 G SR 3 .3 .5 .1 .1 ~! 115 psig Discharge Pressure- SR 3 .3 .5 .1 .2 and High SR 3 .3 .5 .1 .3 1 135 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . ADS Drywell Pressure 1,2 (0 ,3 4) 2 G SR 3 .3 .5 .1 .2 5 6 .5 minutes Bypass Timer SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 Manual Initiation ,2 (T J (d) 2 G SR 3 .3 .5 .1 .5 NA (continued)

(d) With reactor steam dome pressure > 150 psig .

(e) This function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-42 Amendment No .

ECCS Instrumentation 3 .3 .5 . 1 Table 3 .3 .5 .1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE VALUE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS ADS Trip System 2 (Logic B and F) a . Reactor Vessel Water &T NO 2 SR 3 .3 .5 .1 .1 A -148 .1 Level-Low Low Low, SR 3 .3 .5 .1 .2 inches (e)

Level 1 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 b . Drywell Pressure-High YNNT 2 F SR 3 .3 .5 .1 .1 1 1 .88 psig SR 3 .3 .5 .1 .2 SR 3 .3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 c . ADS Initiation Timer 1,2 (0, 3 (d) SR 3 .3 .5 .1 .2 <_ 117 seconds SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 d . Reactor Vessel Water ,2 (M, 3 (d) SR 3 .3 .5 .1 .1 ~~ 8 .3 inches Level-Low, Level 3 SR 3 .3 .5 .1 .2 (Confirmatory) SR 3,3 .5 .1 .3 SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 e . LPCI Pumps B & C ,2 (d) YW 2 per pump G SR 3 .3 .5 .1 .1 ? 115 psig Discharge SR 3 .3 .5 .1 .2 and Pressure-High SR 3 .3 .5 .1 .3 1 135 psig SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 f . ADS Drywell Pressure 1,2(a)N, 2 G SR 3 .3 .5 .1 .2 1 6 .5 minutes Bypass Timer SR 3 .3 .5 .1 .4 SR 3 .3 .5 .1 .5 g . Manual Initiation ,2 (d) , 3 ca) 2 G SR 3 .3 .5 .1 .5 NA (d) With reactor steam dome pressure > 150 psig .

(e) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-43 Amendment No .

RCIC System Instrumentation 3 .3 .5 .2 Table 3 .3 .5 .2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED FROM CHANNELS PER REQUIRED ACTION SURVEILLANCE ALLOWABLE FUNCTION FUNCTION A .1 REQUIREMENTS VALUE Reactor Vessel Water 4 B SR 3 .3 .5 .2 .1 A -48 .1 Level-Low Low, Level 2 SR 3 .3 .5 .2 .2 inches (a)

SR 3 .3 .5 .2 .3 SR 3 .3 .5 .2 .4 SR 3 .3 .5 .2 .5 Reactor Vessel Water 2 C SR 3 .3 .5 .2 .1 5 52 .6 inches Level-High, Level 8 SR 3 .3 .5 .2 .2 SR 3 .3 .5 .2 .3 SR 3 .3 .5 .2 .4 SR 3 .3 .5 .2 .5

3. RCIC Storage Tank 2 D SR 3 .3 .5 .2 .1 ? 3 .0 inches Level-Low SR 3 .3 .5 .2 .2 SR 3 .3 .5 .2 .3 SR 3,3 .5 .2 .4 SR 3 .3 .5 .2 .5 Suppression Pool Water 2 D SR 3 .3 .5 .2 .1 A -5 inches Level-High SR 3 .3 .5 .2 .2 SR 3 .3 .5 .2 .3 SR 3 .3 .5 .2 .4 SR 3 .3 .5 .2 .5

5. Manual Initiation 1 C SR 3 .3 .5 .2 .5 NA (0 This function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-47 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 1 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE VALUE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS Main Steam Line Isolation a . Reactor Vessel Water 1,2,3 4 G SR 3 .3 .6 .1 .1 -148 .1 Level-Low Low Low, SR 3 .3 .6 .1 .2 inches Level 1 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 b . Main Steam Line 1 4 H SR 3 .3 .6 .1 .1 n 840 psig Pressure-Low SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 c . Main Steam Line 1,2,3 4 G SR 3 .3 .6 .1 .1 § 284 psid Flow-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 SR 3 .3 .6 .1 .7 d . Condenser Vacuum-Low ,2", 4 G SR 3 .3 .6 .1 .1 ? 7 .6 inches SR 3 .3 .6 .1 .2 Hg vacuum

, (a) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Main Steam Tunnel 1,2,3 4 G SR 3 .3 .6 .1 .1 1 171*F Temperature-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Main Steam Line Turbine 1,2,3 4 G SR 3 .3 .6 .1 .1 Modules 1-4 Building SR 3 .3 .6 .1 .2 n 142oF, Temperature-High SR 3 .3 .6 .1 .5 Module 5 SR 3 .3 .6 .1 .6 5 150oF g . Manual Initiation 1,2,3 4 1 SR 3 .3 .6 .1 .6 NA (continued)

(a) With any turbine stop valve not closed .

(i) This function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-55 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 2 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE

2. Primary Containment and Drywell Isolation a . Reactor Vessel Water 1,2,3 4 K SR 3 .3 .6 .1 .1 A -48 .1 inches Level-Low Low, Level 2 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 4 0 SR 3 .3 .6 .1 .1  ? -48 .1 inches SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 b . Drywell Pressure-High 1,2,3 SR 3 .3 .6 .1 .1 5 1 .88 psig SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 c . Deleted d . Drywell Pressure-High 1,2,3 4 (b) SR 3 .3 .6 .1 .1 1 1 .88 psig (ECCS Divisions 1 SR 3 .3 .6 .1 .2 and 2) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Reactor Vessel Water 1,2,3 4 1 SR 3 .3 .6 .1 .1  ? -48 .1 `inches 0)

Level-Low Low, Level SR 3 .3 .6 .1 .2 2 (HPCS NSPS Div 3 SR 3 .3 .6 .1 .3 and 4) SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Drywell Pressure-High 1,2,3 4 1 SR 3 .3 .6 .1 .1 i 1 .88 psig (HPCS NSPS Div 3 and SR 3 .3 .6 .1 .2

4) SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (continued)

{W Also required to initiate the associated drywell isolation function .

(C) During operations with a potential for draining the reactor vessel .

(i) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3- 5 6 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 3 of 6)

Mary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE 2 . Primary Containment and Drywell Isolation (continued)

(c), (d) N SR 3 .3 .6 .1 .1 g . Containment Building <_ 500 MR/

Fuel Transfer Pool SET 3 .3 .6 .1 .2 Ventilation Plenum SR 3 .3 .6 .1 .5 Radiation-High SR 3 .3 .6 .1 .6 h . Conta ent Building 1,2,3 SR 3 .3 .6 .1 .1 A 400 mR/hr Exhau SR 3 .3 .6 .1 .2 Radiation-High SET 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (c)AT 4 SR 3 .3 .6 .1 .1 A 400 mR/hr SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 i . Containment Building 1,2,3 SR 3 .3 .6 .1 .1 1 400 mR/hr Continuous Containment SR 3 .3 .6 .1 .2 Purge (CCP) Exhaust SR 3 .3 .6 .1 .5 Radiation-High SR 3 .3 .6 .1 .6 (N, (d) SR 3 .3 .6 .1 .1 5 400 MR/

SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 j . Reactor Vessel Water 1,2,3 SR 3 .3 .6 .1 .1 A -148 .1 inches 0)

Level-Low Low Low, SR 3 .3 .6 .1 .2 Level 1 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (c) SR 3 .3 .6 .1 .1 0 ~! -148 .1 inches SET 3 .3 .6 .1 .2 SET 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (e) k . Containment Pressure- SR 3 .3 .6 .1 .1 <_ 3 .0 psid High SET 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 iation 1,2,3 2 (b) IT SR 3 .3 .6 .1 .6 MA (01(w 2 11 SR 3 .3 .6 .1 .6 MA (continued)

(b) Also required to itiate the associated drywell isolation function .

ing operations with a potential for draining the reactor vessel .

(d) During movement of recently adiated fuel assemblies in the primary or secondary containment .

(e) MODES 1, 2, and 3 with the associated PCIVs not closed .

(i) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3- 5 7 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 4 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE 3 . Reactor Core Isolation Cooling (RCIC) System Isolation a . Auxiliary Building 1,2,3 2 1 SR 3 .3 .6 .1 .1 1 118 .5 inches RCIC Steam Line SR 3 .3 .6 .1 .2 water Flow-High SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 b . RCIC Steam Line 1,2,3 2 1 SR 3 .3 .6 .1 .2 1 13 seconds Flow-High, SR 3 .3 .6 .1 .5 Time Delay SR 3 .3 .6 .1 .6 c . RCIC Steam Supply Line 1,2,3 2 1 SR 3 .3 .6 .1 .1 i 52 psig Pressure-Low SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 d . RCIC Turbine Exhaust 1,2,3 4 1 SR 3 .3 .6 .1 .1 0 20 psig Diaphragm SR 3 .3 .6 .1 .2 Pressure-High SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . RCIC Equipment Room 1,2,3 2 1 SR 3 .3 .6 .1 .1 A 207*F Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Main Steam Line Tunnel 1,2,3 2 1 SR 3 .3 .6 .1 .1 S 171'F Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 g . Main Steam Line Tunnel 1,2,3 2 1 SR 3 .3 .6 .1 .2 A 28 minutes Temperature Timer SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 h . Reactor Vessel Water 1,2,3 4 1 SR 3 .3 .6 .1 .1 1 -48 .1 inches 0)

Level-Low Low, Level 2 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 i . Drywell RCIC Steam 1,2,3 2 1 SR 3 .3 .6 .1 .1 5 188 inches Line Flow - High SR 3 .3 .6 .1 .2 water SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (continued)

(i) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3- 58 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 5 of 6) ary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE UNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE

3. RCIC System Isolation (continued) j . Drywell Pressure - High 1,2,3 2 1 SR 3 .3 .6 .1 .1 i 1 .88 psig SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 k . Manual Initiation 1,2,3 1 1 SR 3 .3 .6 .1 .6 NA Reactor Water Cleanup (RWCU) System Isolation a . Differential Flow - 1,2,3 2 1 SR 3 .3 .6 .1 .1 1 66 .1 gpm High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 b . Differential Flow-Timer 1,2,3 2 1 SR 3 .3 .6 .1 .2 a 47 seconds SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .6 c . RWCU Heat Exchanger 1,2,3 2 per I SR 3 .3 .6 .1 .1 1 205*F Equipment Room room SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 d . RWCU Pump Rooms 1,2,3 2 per I SR 3 .3 .6 .1 .1 A 202OF Temperature-High room SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Main Steam Line Tunnel 1,2,3 2 1 SR 3 .3 .6 .1 .1 5 171OF Ambient Temperature- SR 3 .3 .6 .1 .2 High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Reactor Vessel Water 1,2,3 4 1 SR 3 .3 .6 .1 .1 1 -48 .1 inches Level-Low Low, SR 3 .3 .6 .1 .2 Level 2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 (C) 4 0 SR 3 .3 .6 .1 .1 A -48 .1 inches SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 g . Standby Liquid Control 1,2 2 L SR 3 .3 .6 .1 .6 NA System Initiation h . Manual Initiation 1,2,3 2 j SR 3 .3 .6 .1 .6 NA (01(a) 2 N SR 3 .3 .6 .1 .6 NA (continued)

(C) During operations with a potential for draining the reactor vessel .

(d) During movement of recently irradiated fuel assemblies in the primary or secondary containment .

(i) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3- 5 9 Amendment No .

Primary Containment and Drywell Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 6 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F .1 REQUIREMENTS VALUE 5 . RHR System Isolation a . RHR Heat Exchanger 1,2,3 2 per room I SR 3 .3 .6 .1 .1 1 160OF Ambient SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 b . Reactor Vessel Water 1,2,3 0) 4 1 SR 3 .3 .6 .1 .1 A 8 .3 inches Level - Low, Level 3 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6-1 .5 SR 3 .3 .6 .1 .6 C . Reactor Vessel water 3q ) ,4,5 4 0) M SR 3 .3 .6 .1 .1 ! 8 .3 inches Level - Low, Level 3 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3-6 .1 .5 SR 3 .3 .6 .1 .6 d . Reactor Vessel Water 1,2,3 4 1 SR 30 .6 .1 .1 ? -148 .1 inches Level - Low Low Low, SR 3 .3 .6 .1 .2 Level 1 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 e . Reactor Vessel 1,2,3 4 1 SR 3 .3 .6 .1 .1 n 110 psig Pressure-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 f . Drywell Pressure-High 1,2,3 8 1 SR 3 .3 .6 .1 .1 A 1 .88 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .3 SR 3 .3 .6 .1 .5 SR 3 .3 .6 .1 .6 g . Manual Initiation 1,2,3 2 1 SR 3 .3 .6 .1 .6 NA (f) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure .

(g) With reactor steam dome pressure less than the RHR cut in permissive pressure .

(h) only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained .

(i) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3- 6 0 Amendment No .

Secondary Containment Isolation Instrumentation 3 .3 .6 .2 Table 3 .3 .6 .2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED CHANNELS OTHER SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE Reactor Vessel Water 1,2,3,(a) 2 SR 3 .3 .6 .2 .1 A -48 .1 inches 0)

Level-Low Low, Level 2 SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .3 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5

2. Drywell Pressure-High 1,2,3 2 SR 3 .3 .6 .2 .1 1 .88 prig SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .3 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5 Containment Building Fuel (a),(b) 2 SR 3 .3 .6 .2 .1 0 500 mR/hr Transfer Pool Ventilation SR 3 .3 .6 .2 .2 Plenum Exhaust SR 3 .3 .6 .2 .4 Radiation-High SR 3 .3 .6 .2 .5 Containment Building 1,2,3, 2 SR 3 .3 .6 .2 .1 ! 400 mR/hr Exhaust Radiation-High (a),(b) SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5

5. Containment Building 1,2,3, 2 SR 3 .3 .6 .2 .1 i 400 mR/hr Continuous Containment (ah(b) SR 3 .3 .6 .2 .2 Purge (CCP) Exhaust SR 3 .3 .6 .2 .4 Radiation-High SR 3 .3 .6 .2 .5

6. Fuel Building Exhaust 1,2,3, 2 SR 3 .3 .6 .2 .1 A 17 mR/hr Radiation-High (c) SR 3 .3 .6 .2 .2 SR 3 .3 .6 .2 .4 SR 3 .3 .6 .2 .5 Manual Initiation 1,2,3, 1 SR 3 .3 .6 .2 .5 NA (a),(b)

(a) ations with a potential for draining the reactor vessel .

(b) Dur movement of recently irradiated fuel assemblies e primary or secondary containment .

(c) During movement of recently irradiated fuel assemblies in the fuel building .

(d) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-64 Amendment No .

RHR Containment Spray System Instrumentation 3 .3 .6 .3 Table 3 .3 .6 .3-1 (page 1 of 1)

RER Containment Spray System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION SYSTEM ACTION A .1 REQUIREMENTS VALUE n Drywell Pressure-High 2 13 SR 3 .3 .6 .3 .1 1 1 .88 psig SR 3 .3 .6 .3 .2 SR 3 .3 .6 .3 .3 SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5

n Containment Pressure-High 2 13 SR 3 .3 .6 .3 .1 1 22 .4 psia SR 3 .3 .6 .3 .2 SR 3 .3 .6 .3 .3 SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5 Reactor Vessel Water 2 13 SR 3 .3 .6 .3 .1 A -148 .1 inches Level-Low Low Low, SR 3 .3 .6 .3 .2 Level 1 SR 3 .3 .6 .3 .3 SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5

,n Timers, System A C SR 3 .3 .6 .3 .2 1 10 .10 minutes and and System B SR 3 .3 .6 .3 .4 5 10 .23 minutes SR 3 .3 .6 .3 .5 System B Only 1 C SR 3 .3 .6 .3 .2

5. Timer, 5 90 .6 seconds SR 3 .3 .6 .3 .4 SR 3 .3 .6 .3 .5

6. Manual Initiation C SR 3 .3 .6 .3 .5 NA This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-68 Amendment No .

SPMU System Instrumentation 3 .3 .6 .4 Table 3 .3 .6 .4-1 (page 1 of 1)

Suppression Pool Makeup System Instrumentation REQUIRED CONDITIONS CHANNELS REFERENCED PER FROM TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION SYSTEM ACTION A .1 REQUIREMENTS VALUE Drywell Pressure-High 2 B SR 3 .3 .6 .4 .1 5 1 .88 psig SR 3 .3 .6 .4 .2 SR 3 .3 .6 .4 .3 SR 3 .3 .6 .4 .6 SR 3 .3 .6 .4 .7

2. Reactor vessel water 2 B SR 3 .3 .6 .4 .1 2 -148 .1 inches 0)

Level-Low Low Low, SR 3 .3 .6 .4 .2 Level 1 SR 3 .3 .6 .4 .3 SR 3 .3 .6 .4 .6 SR 3 .3 .6 .4 .7

3. Suppression Pool Water 2 B SR 3 .3 .6 .4 .1 A 29 inches Level-Low Low SR 3 .3 .6 .4 .2 SR 3 .3 .6 .4 .4 SR 3 .3 .6 .4 .6 SR 3 .3 .6 .4 .7 er C SR 3 .3 .6 .4 .2 5 30 minutes SR 3 .3 .6 .4 .5 SR 3 .3 .6 .4 .7

5. Manual Initiation 2 C SR 3 .3 .6 .4 .7 NA (a) This Function is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint .

CLINTON 3 .3-72 Amendment No .

Relief and LLS Instrumentation 3 .3 .6 .5 SURVEILLANCE REQUIREMENTS

---

NOTE -------------------------------------

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 LLS or relief initiation capability, as applicable .

SURVEILLANCE FREQUENCY SR 3 .3 .6 .5 .1 Perform CHANNEL FUNCTIONAL TEST . 92 days SR 3 .3 .6 .5 .2 Calibrate the analog trip module . 92 days SR 3 .3 .6 .5 .3 Perform CHANNEL CALIBRATION . The 18 months Allowable values shall be :

a . Relief Function Low : 5 1118 psig Medium : 1 1128 psig High : i 1138 psig b . LLS Function Low open : 1 1044 psig close : 5 937 psig Medium open :  ! 1084 psig close : 1 947 psig High open : 5 1124 psig close : 5 957 psig SR 3 .3 .6 .5 .4 Perform LOGIC SYSTEM FUNCTIONAL TEST . 18 months CLINTON 3 .3-74 Amendment No .