ML18330A095

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Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005
ML18330A095
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/30/2018
From: Marshall M
Plant Licensing Branch 1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Marshall M, NRR/DORL/LPL1
References
Download: ML18330A095 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 30, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 1 - CORRECTION RE: DUPLICATE NOTE (N) ON TECHNICAL SPECIFICATION PAGE 204 THAT OCCURRED IN AMENDMENT NO. 186 ISSUED JANUARY 25, 2005

Dear Mr. Hanson:

In reviewing the Nine Mile Point Nuclear Station, Unit 1, current Technical Specifications (TSs)),

it was determined that Note (n) for Tables 3.6.2a and 4.6.2a, which states "Deleted," on TS page 204, should have been removed upon issuance of Amendment No. 186 on January 25, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No.

ML043440114). Amendment No. 186 revised Note (n) on page 203 to state, "Neutron detectors are excluded."

The duplication of a second Note (n) on TS page 204 remained during issuance of Amendment No. 222 on May 31, 2016 (ADAMS Accession No. ML16081A256), where numerous TS pages were updated, including TS pages 203 and 204.

A corrected TS page 204 is enclosed that removes Note (n), which states "Deleted." This correction involves an oversight that was carried forward on a duplicate Note (n) that should have been removed on issuance of Amendment No. 186 and does not change any of the conclusions in the safety evaluations associated with the issuance of Amendment Nos. 186, 222, or any amendments issued subsequent to Amendment Nos. 186 and 222 for the Nine Mile Point Nuclear Station, Unit 1.

B. Hanson If you have any questions, please contact me at 301-415-2871 or Michael.Marshall@nrc.gov.

Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Corrected TS page 204 cc: Listserv

Enclosure Corrected TS page 204 (Nine Mile Point Nuclear Station, Unit 1)

NOTES FOR TABLES 3.6.2a and 4.6.2a (o) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same trip system is monitoring that parameter.

With one channel required by Table 3.6.2a inoperable in one or more Parameters, place the inoperable channel and/or that trip system in the tripped condition* within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With two or more channels required by Table 3.6.2a inoperable in one or more Parameters:

1. Within one hour, verify sufficient channels remain Operable or tripped* to maintain trip capability for the Parameter, and
2. Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, place the inoperable channel(s) in one trip system and/or that trip system** in the tripped condition*, and
3. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, restore the inoperable channels in the other trip system to an Operable status or tripped*.

Otherwise, take the ACTION required by Specification 3.6.2a for that Parameter.

  • An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to Operable status within the required time, the ACTION required by Specification 3.6.2a for the parameter shall be taken.
    • This ACTION applies to that trip system with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION can be applied to either trip system.

(p) May be bypassed during reactor coolant system pressure testing and/or control rod scram time testing.

Note 1: Surveillance intervals are specified in the Surveillance Frequency Control Program unless otherwise noted in Table 4.6.2a AMENDMENT NO. ~ . 222 204

ML18330A095 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME MMarshall LRonewicz JDanna MMarshall DATE 11/26/18 11/26/18 11/30/18 11/30/18