ML083170048
| ML083170048 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/26/2008 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Rencheck M Indiana Michigan Power Co |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| Download: ML083170048 (5) | |
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~O November 26, 2008
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Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION OF TYPOGRAPHICAL ERROR RE: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0.7
Dear Mr. Rencheck:
On June 1, 2005, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 287 and 269 to Facility Operating Licenses DPR-58 and DPR-74, respectively, for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML050620034). The amendments approved the conversion of the Technical Specifications (TS) to Improved Technical Specifications (ITS) consistent with NUREG-1431, "Standard Technical Specification - Westinghouse Plants,"
Revision 2.
Indiana Michigan Power Company staff subsequently identified a typographical error in the TSs which occurred during the ITS conversion and requested correction of this error in a letter dated October 21,2008 (ADAMS Accession No. ML082970188). Specifically, LCO Applicability 3.0.7 currently states LCO 3.1.8, "PHYSIC TESTS Exceptions - MODE 2," but should state LCO 3.1.8, "PHYSICS TESTS Exceptions - MODE 2" (balded and italicized for emphasis).
The NRC staff determined that this error was inadvertently introduced. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments and does not affect the associated notice to the public.
A corrected TS Page 3.0-2 for CNP Unit 1 and CNP Unit 2 is enclosed. If you or your staff has any questions, please call me at 301-415-3049.
A
~tIi Terry A. Beltz, Senior Project Manager Plant Licensing Branch '"-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315 and 50-316
Enclosure:
As stated cc w/encl: Distribution via ListServ
ENCLOSURE CORRECTED PAGE 3.0-2 FOR AMENDMENT NO. 287 FACILITY OPERATING LICENSE NO. DPR-58 DONALD C. COOK NUCLEAR PLANT, UNIT 1
-AND CORRECTED PAGE 3.0-2 FOR AMENDMENT NO. 269 FACILITY OPERATING LICENSE NO. DPR-74 DONALD C. COOK NUCLEAR PLANT, UNIT 2
LCD Applicability 3.0 3.0 LCD Applicability LCD 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.
LCD 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 LCD 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
LCD 3.0.6 When a supported system LCD is not met solely due to a support system LCD not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCD ACTIONS are required to be entered. This is an exception to LCD 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 LCD 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 LCD 3.0.2.
LCD 3.0.7 Test Exception LCD 3.1.8, "PHYSICS 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 LCD is desired to be met but is not met, the ACTIONS of the Test Exception LCD shall be met. When a Test Exception LCD 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.
Cook Nuclear Plant Unit 1 3.0-2 Amendment No. 287 Corrected by letter dated Nmrember 26
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2008
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, "PHYSICS 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.
Cook Nuclear Plant Unit 2 3.0-2 Amendment No. 269 Corrected by letter dated November 26, 2008
November26 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUB-JECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION OF TYPOGRAPHICAL ERROR RE: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0.7
Dear Mr. Rencheck:
On June 1, 2005, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 287 and 269 to Facility Operating Licenses DPR-58 and DPR-74, respectively, for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML050620034). The amendments approved the conversion of the Technical Specifications (TS) to Improved Technical Specifications (ITS) consistent with NUREG-1431, "Standard Technical Specification - Westinghouse Plants,"
Revision 2.
Indiana Michigan Power Company staff subsequently identified a typographical error in the TSs which occurred during the ITS conversion and requested correction of this error in a letter dated October 21,2008 (ADAMS Accession No. ML082970188). Specifically, LCO Applicability 3.0.7 currently states LeO 3.1.8, "PHYSIC TESTS Exceptions - MODE 2," but should state LCO 3.1.8, "PHYSICS TESTS Exceptions - MODE 2" (balded and italicized for emphasis).
The NRC staff determined that this error was inadvertently introduced. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments and does not affect the associated notice to the public.
A corrected TS Page 3.0-2 for CNP Unit 1 and CNP Unit 2 is enclosed. If you or your staff has any questions, please call me at 301-415-3049.
Sincerely, lRAI Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
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