ML110970219

Correction to Issuance of License Amendments Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a License-controlled Program

ML110970219
Person / Time
Site:	Clinton
Issue date:	05/06/2011
From:	Nicholas Difrancesco Plant Licensing Branch III
To:	Pacilio M Exelon Nuclear
DiFrancesco N, NRR/DORL/LPL3-2, 415-1115
References
TAC ME3332
Download: ML110970219 (11)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 6. 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

CLINTON POWER STATION, UNIT NO. 1- CORRECTION TO ISSUANCE OF LICENSE AMENDMENTS REGARDING RISK-INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE-CONTROLLED PROGRAM (TAC NO. ME3332)

Dear Mr. Pacilio:

By letter dated February 15, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102380477), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No.1 (CPS). The amendment adopted the NRC-approved Technical Specification Task Force (TSTF-425), Revision 3, "Relocate Surveillance Frequencies to Licensee Control RITSTF Initiative 5b," in response to your application dated February 15, 2010 (ADAMS Accession No. ML100470787), as supplemented by letter dated May 21, 2010 (ADAMS Accession No. ML101450001).

The TSTF-425 relocates most periodic frequencies of Technical Specifications (TS) surveillances to a licensee-controlled program, the Surveillance Frequency Control Program, and provides requirements for the new program in the Administrative Controls section of the TS.

After issuance, it became apparent that TS pages 3.3-54a, 3.3-54b, 3.3-72, 3.3-73, 3.3-74a, and 3.3-74b were omitted in the approval letter, dated February 15,2011. Furthermore, the facility operating license (FOL) was issued incorrectly, and Note (3) was not removed from surveillance requirement (SR) 3.3.1.1.17, as requested in your license submittal.

Enclosed are the corrected FOL Page 3, the corrected SR 3.3.1.1.17 (TS page 3.3-6) with Note (3) removed, and the omitted TS pages. This error did not impact Amendment No. 192 as these are administrative corrections and does not change the NRC staff conclusions.

M. Pacilio - 2 We regret any inconvenience this may have caused. Should you have any questions regarding this matter, please call me at (301) 415-1115.

~g.j5 Nicholas J. DiFrancesco, Project ManGlger Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-461 cc: Distribution via Listserv

• 3*

(4) exelon Generation Company, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup. sealed sources for reactor instrumentation and radiation monitoring equipment calibration. and as fission detectors in amounts as required:

(5) Exelon Generation Company. pursuant to the Act and 10 CFR Parts 30.

40, and 70, to receive, possess, and use In amounts as required any byproduct. source or special nuclear material without restriction to chemical or physical form, for sample analysiS or instrument calibration or associated with radioactive apparatus or components; (6) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30.

40, and 70, to possess, but not separate. such byproduct and special nuclear materials as may be produced by the operation of the facility.

Mechanical disassembly of the GE1411sotope test assemblies containing Cobalt-60 is not conSidered separation; and (7) exelon Generation Company, pursuant to the Act and 10 CFR Part 30. to intentionany produce. possess, receive, transfer, and use Cobalt-60.

C. This license shall be deemed to contain and is subject to the condhions specified In the Commission's regulations set forth in 10 CFR Chapter I and Is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter In effect; and is subject to the additional cond~lons specified or Incorporated below:

(1) Maxlmym Power Level Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical SpecHications and Enyironmental Protection Pion The TechnlcCll Specifications contained In AppendiX A and the Envlronmenlal PrOlectlon DI"Vl contained In Appendix 6. as revised through Amendment No. 192. are hereby incorporated into this license.

Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 192

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.16 Verify Turbine Stop Valve Closure and In accordance Turbine Control Valve Fast Closure Trip with the Oil Pressure-Low Functions are not Surveillance bypassed when THERMAL POWER is > 33.3% Frequency RTP. Control Program SR 3.3.1.1.17 -----------------NOTES-----------------

1. Neutron detectors are excluded.

2. For Functions 3, 4, and 5 in Table 3.3.1.1-1, the channel sensors are excluded.

Verify the RPS RESPONSE TIME is within In accordance limi ts. with the Surveillance Frequency Control Program CLINTON 3.3-6 Amendment No. 192

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.7 --NOTE-------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME In accordance for the main steam isolation valves is with the within limits. Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program CLINTON 3.3-S4a Amendment No. 192

This page intentionally left blank CLINTON 3.3-S4b Amendment No. 192

SPMU System Instrumentation 3.3.6.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.4.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.4.8 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program CLINTON 3.3-72 Amendment No. 192

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

1. Drywell Pressure-High 2 B SR 3.3.6.4.1 0; 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

'-'= -148.1 inches Level-Low Low Low, SR 3.3.6.4.2 Level 1 SR 3.3.6.4.3 SR 3.3.6.4.7 SR 3.3.6.4.8

3. Suppression Pool Water 2 B SR 3.3.6.4.1 2' 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

4. Timer 1 C SR 3.3.6.4.2 0; 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 CLINTON 3.3-73 Amendment No. 192

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. In accordance with the Surveillance Frequency Control Program

--NOTES

1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpointi otherwise, the channel shall be declared inoperable.

3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

SR 3.3.6.5.2 Calibrate the analog trip module. In accordance with the Surveillance Frequency Control Program (continued)

CLINTON 3.3 74a Amendment No. 192

Relief and LLS Instrumentation 3.3.6.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE Frequency

---

NOTES

1. If the as found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpointj otherwise, the channel shall be declared inoperable.

3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

SR 3.3.6.5.3 Perform CHANNEL CALIBRATION. The In accordance Allowable Values shall be: with the Surveillance

a. Relief Function Frequency Control Program Low: < 1118 psig Medium: < 1128 psig High: < 1138 psig

b. LLS Function Low open: < 1044 psig close: < 937 psig Medium open: < 1084 psig close: ::: 947 psig High open: < 1124 psig close: ::: 957 psig SR 3.3.6.5.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program CLINTON 3.3-74b Amendment No. 192

M. Pacilio - 2 We regret any inconvenience this may have caused. Should you have any questions regarding this matter, please call me at (301) 415-1115.

Sincerely, IRA!

Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-461 cc: Distribution via Listserv DISTRIBUTION:

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DATE 05/05/11 05/05/11 05/03/11 05/06/11 OFFICIAL RECORD COpy