ML111660815

Correction Letter License Amendment No. 157

ML111660815
Person / Time
Site:	Perry
Issue date:	06/16/2011
From:	Michael Mahoney Plant Licensing Branch III
To:	Bezilla M FirstEnergy Nuclear Operating Co
mahoney, m NRR/DORL/LPLIII-2 415-3867
References
Download: ML111660815 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

..Jure 16, 2Dl1 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry,OH 44081-0097 SUB~IECT: PERRY NUCLEAR POWER PLANT, UNIT NO.1 - CORRECTION LETTER RE: LICENSE AMENDMENT NO. 157

Dear Mr. Bezilla:

On May 19, 2011 the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 157 to Facility Operating License (FOL) No. NPF-58 for the Perry Nuclear Power Plant (PNPP), Unit No.1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11105A0380). This license amendment modified the requirements for testing control rod scram times following fuel movement within the reactor pressure vessel by incorporating the NRC approved Technical Specification Task Force (TSTF) change traveler TSTF-222-A, Revision 1.

Also, on May 19, 2011, the NRC issued Amendment No. 156 to FOL No. NPF-58 for PNPP (ADAMS Accession No. ML1110502670). This license amendment modifies the required testing frequency of Surveillance Requirement 3.1.4.2 from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1," by incorporating NRC-approved T TSTF-460, Revision O.

Amendment No. 156 made changes on the same Technical Specification (TS) page (TS 3.1-13) as Amendment No. 157. Since both amendments were issued so close to each other, Amendment No. 157 TS changes did not reflect the Amendment No. 156 changes. Therefore the TS pages (3.1-12 and 3.1-13) for Amendment No. 157 are being reissued by this letter, with the Amendment No. 156 changes incorporated.

M. Bezilla - 2 If you have any questions, please call me at 301-415-3867 or MichaeI.Mahoney@nrc.gov.

Sincerely, Michael Mahoney, Project Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

Corrected Amendment No. 157 to NPF-58 cc w/encis: Distribution via Listserv

Control Rod Scram Times 3.l.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.l.4 a. No more than 13 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and

b. No OPERABLE control rod that is"slow" sha 11 occupy a location adjacent to another OPERABLE control rod that is "slow" or a withdrawn control rod that is stuck.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.l Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> LCO not met.

SURVEILLANCE REQUIREMENTS

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

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.l.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure ~ 950 psig. 40% RTP after each reactor shutdown

~ 120 days (continued)

PERRY - UN IT 1 3.1-12 Amendment No. 157

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample. each 200 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam ogeration in dome pressure ~ 950 psig. MDE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control .rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding 40%

reactor steam dome pressure ~ 950 psig. RTP after fuel Illovement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time PERRY - UN IT 1 3.1-13 Amendment No. 15T

ML111660815 NRR-106 OFFICE DORULPL3-21PM DORLlLPL3-21LA DORULPL3-21BC NAME MMahoney SRohrer JZimmerman DATE 6/15/11 6/15/11 6/16/11