AEP-NRC-2016-09, Correction of Technical Specification Typographical Error

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Correction of Technical Specification Typographical Error
ML16020A451
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/15/2016
From: Scarpello M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2016-09, TAC MF5696, TAC MF5697
Download: ML16020A451 (10)


Text

-INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWVER One Cook Place A

unt ofAmercan lectic PwerBridgman, MI 49106 A unt o

Amnca Elctrc PwerIndianaMichiganPower~com January 15, 2016 AEP-NRC-201 6-09 10 CFR 50.4 Docket-No.: 50-315 U. S. Nuclear Regulatory Commission A-I-IN: Document Control Desk Washington, DC, 20555-0001 Donald C. Cook Nuclear Pltant Unit 1 Correction of Technical Specification Typographical Error

References:

1. Letter from Q. S. Lies, Indiana Michigan Power (I&M), to U. S. Nuclear Regulatory--

Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, License Amendment Request to Adopt TSTF-427, Revision 2, 'Allowance for Non Technical Specification Barrier Degradation on Supported System Operability'," dated February 6, 2015, Agencywide Documents Access Management System (ADAMS)

Accession Number ML15041A069.

2. Letter from A. Dietrich, NRC, to L. J. Weber, l&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Amendments RE: Adoption of TSTF-427, 'Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability,' Revision 2 (TAC Nos. MF5696 and MF5697)," dated April 6, 2015, ADAMS Accession Number ML15076A226.
3. Proposed Guidance for Correction of Technical Specification Typographical Errors, SECY-96-238, dated November 19, 1996.

This letter requests the U. S. Nuclear Regulatory Commission's (NRC) approval of a correction to typographical errors in Donald C. Cook Nuclear Plant (CNP) Unit 1 Technical Specifications (TS) which were inadvertently introduced during License Amendment 327 (Reference 2).

These typographical errors were not addressed in the notice to the public, nor reviewed by the NRC, and fall within the scope of guidance provided in SECY-96-238 (Reference 3) for corrections. describes the typographical errors and corrections. Enclosure 2 provides a mark-up of the TS page. Enclosure 3 provides a clean copy of the TS page. Indiana Michigan Power, the licensee for CNP,_will issue the change notification to all holders of controlled copies of CNP TSs upon receipt of NRC approval of these corrections.

U. S. Nuclear Regulatory Commission AEP-NRC-201 6-09 Page 2 This letter contains no new commitments.

If you have any questions or require additional information, please contact me at (269) 466-2649.

Sincerely, Michael K. Scarpello Regulatory Affairs Manager DMB/mll

Enclosures:

1. Description of Technical Specification Typographical Errors
2.

Mark-up Technical Specification Pages Correcting the Typographical Errors

3. Clean Copy of Technical Specification Pages Correcting the Typographical Errors c:

R. J. Ancona, MPSC A. W. Dietrich, NRC, Washington, D.C.

MDEQ - RMD/RPS NRC Resident Inspector C. D. Pederson, NRC, Region Ill A. J. Williamson, AEP Ft. Wayne, w/o enclosures

ENCLOSURE I TO AEP-NRC-2016-09 Description of Technical Specification Typographical Errors A.

Requested Action Consistent with the information contained in SECY-96-238, Proposed Guidance for Correction of Technical Specification Typographical Errors, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 1, is requesting correction for an inadvertent typographical error that was introduced into the CNP Technical Specification (TS) header on two pages.

B.

Typographical Error A typographical error was introduced into the CNP TSs during implementation of Unit 1 License Amendment 327 (Reference 2). The specification of the error and proposed correction are described below:

Unit 1 Page 3.0-2 and Unit 1 Page 3.0-3 The header-on Page 3.0-2 and 3.0-3 references "SR Applicability 3.0." The header for both of these pages should reference "LCO Applicability 3.0."

This error was not introduced in the original License Amendment Request (LAR)

Mark-up pages.(Reference 1) that were submitted to the U. S. Nuclear Regulatory Commission (NRC) and was, therefore, not noticed to the public, nor approved by the NRC during review and approval of Amendment 327. This error was introduced on the clean pages issued after NRC review.

C.

Corrections to the Affected TS Paqe SECY 96-238, (Reference 3) provides guidance to correct inadvertent typographical errors in the TS pages. Specifically:

"... the staff or licensee can demonstrate that the error was introduced inadvertently in a particular license* amendment and that the erroneous change was not addressed in the notice to the public nor reviewed by the staff.

Under these limited circumstances, the change that introduced the typographical error was not a proper amendment to the license because it was neither addressed in the notice nor reviewed, and correction of the typographical error is not a "change" to the TS. Accordingly, the typographical error may be corrected by a letter to the licensee from the NRC staff, instead of an amendment to the license...

The above typographical errors were not noticed to the public, nor reviewed by the NRC as part of the application amendment process.

Therefore, these errors may be corrected wi~hout a license amendment.

Accordingly, upon approval from the NRC, a corrected Unit 1 TS Page 3.0-2 and Page 3.0-3 will be issued to all holders of controlled TS.

to AEP-NRC-2016-09 Pg Page 2 D.

References

1. Letter from Q. S. Lies, Indiana Michigan Power (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Controi Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, License Amendment Request to Adopt TSTF-427, Revision 2,'Allowance for Non Technical Specification Barrier Degradation on Supported System Operability',"

dated February 6, 2015, Agencywide Documents Access Management System (ADAMS) Accession Number ML15041A069.

2.

Letter from A. Dietrich, NRC, to L. J. Weber, l&M, "Donald C. Cook Nuclear Plant, Units I and 2 - Issuance of Amendments RE: Adoption of TSTF-427, 'Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability,'

Revision 2 (TAC Nos. MF5696 and MF5697)," dated April 6, 2015, ADAMS Accession Number ML15076A226.

3. Proposed Guidance for Correction of Technical Specification Typographical. Errors, SECY-96-238, dated November 19, 1996.

ENCLOSURE 2 TO AEP-NRC-2016-09 DONALD C. COOK NUCLEAR PLANT UNIT 1 MARK-UP TECHNICAL SPECIFICATION PAGES CORRECTING THE TYPOGRAPHICAL ERRORS

00Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

c.

When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8, "PHYSIC TESTS Exceptions - MODE 2,"

allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support Cook Nuclear Plant Unit 1 mnmntN.27 2

3.0-2 Amendment No. 2-87-, 327

E LOApplicability 3.0 3.0 LCO Applicability LCO 3.0.8 (continued) function(s), and risk is assessed and managed. This specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.

If the required OPERABLE train or subsystem becomes inoperable while this specification is in use, it must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the provisions of this specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s).

At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.

Cook Nuclear Plant Unit 1 mnmntN.27 2

3.0-3 Amendment No. 28-7-, 327

ENCLOSURE 3 TO AEP-NRC-2016-09 DONALD C. COOK NUCLEAR PLANT UNIT 1 CLEAN COPY OF TECHNICAL SPECIFICATION PAGES CORRECTING TYPOGRAPHICAL ERRORS

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

c.

When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the Supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program; the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8, "PHYSIC TESTS Exceptions - MODE 2,"

allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support Cook Nuclear Plant Unit I1.-

mnmntN.27 2

3.0-2 Amendment No. 287, 327

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.8 (continued) function(s), and risk is assessed and managed. This specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.

If the required OPERABLE train or subsystem becomes inoperable while this specification is in use, it must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the provisions of this specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s).

At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.

Cook Nuclear Plant Unit 1 mnmntN.27 2

3.0-3 Amendment No. 2-8-7, 327