ML11105A038
| ML11105A038 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/19/2011 |
| From: | Michael Mahoney Plant Licensing Branch III |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| Mahoney M | |
| References | |
| TAC ME5192, TSTF-222 | |
| Download: ML11105A038 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 19. 2011 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
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO.1 - ISSUANCE OF AMENDMENT RE: LICENSE AMENDMENT TO MODIFY TECHNICAL SPECIFICATION 3.1.4. "CONTROL ROD SCRAM." TO INCORPORATE TECHNICAL SPECIFICATION TASK FORCE (TSTF) CHANGE TRAVELER TSTF-222 (TAC NO. ME5192)
Dear Mr. Bezilla:
The U.S. Nuclear Regulatory Commission (NRC. the Commission) has issued the enclosed Amendment No. 157 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant. Unit NO.1. This amendment revises the technical specifications in response to your application dated December 15, 2010 (Agencywide Documents Access and Management System Accession No. ML103630423).
This license amendment modifies the requirements for testing control rod scram times following fuel movement within the reactor pressure vessel by incorporating the NRC approved TSTF-222-A, Revision 1.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Michael Mahoney. Proj t Manager Plant Licensing Bran 111-2 Division of Operatin Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 157 to NPF-58
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 157 License No. NPF-58
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for license filed by FirstEnergy Nuclear Operating Company, et aI., (the licensee, FENOC) dated December 15, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2}
of Facility Operating License No. NPF-58 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 157 are hereby incorporated into this license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9~!~C::f
~~ltLicensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
May 19, 2011
ATTACHMENT TO LICENSE AMENDMENT NO. 157 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-58 License NPF-58 Page 4 Page 4 TSs TSs 3.1-12 3.1-12 3.1-13 3.1-13
-2 renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license.
(b)
Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions 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 and hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 157, are hereby incorporated into the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions
- a. FirstEnergy Nuclear Generation Corp. and Ohio Edison Company Amendment No. 157
Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4
- 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" shall 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 LCD not met.
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 /> SURVEILLANCE REQUIREMENTS
- -------------------------------- --NO-rE----
During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
SURVEILLANCE SR 3.1.4.1 Verify each control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 950 psig.
FREQUENCY Prior to*
exceeding 40% RTP after each reactor shutdown
~ 120 days (continued)
PERRY - UNIT 1
- 3.
12 Amendment NO*157 I
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample. each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 950 psig.
120 days cumulative operation in MODE 1 SR 3.1.4.3 Verify each affected control rod scram time is within the limits of Table 3.1.4-1 with any reactor steam dome pressure.
Prior to declaring 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 is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 950 psig.
Prior to exceeding 40%
RTP after fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRO System that could affect scram time PERRY UNIT 1 3.1-13 Amendment No. 157 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 157 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO.1 DOCKET NO. 50-440
1.0 INTRODUCTION
By application dated December 15, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103630423), FirstEnergy Nuclear Operating Company, (the licensee) submitted a license amendment request, regarding Perry Nuclear Power Plant, Unit 1, to modify Technical SpeCification (TS) 3.1.4, "Control Rod Scram Times," to incorporate Technical Specification Task Force (TSTF) change traveler TSTF-222-A, Revision 1.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission's (NRC, the Commission) regulatory requirements related to the content of the TS are contained in Section 50.36, "Technical specifications," of Title 10 of the Code of Federal Regulations (10 CFR). The regulations in 10 CFR 50.36 require that the TS include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
The regulations in 10 CFR 50.36(c)(3) state that SRs "are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The licensee's proposed changes revise SRs for control rod scram time testing found in TS 3.1.4, "Control Rod Scram Times."
These proposed changes were reviewed for compliance with 10 CFR 50.36(c)(3).
3.0 TECHNICAL EVALUATION
The licensee has proposed to adopt TSTF-222-A, Revision 1 (ADAMS Accession No. ML040570118). TSTF-222-A, Revision 1, was submitted to the NRC on April 28, 1998, and was approved for plant-specific adoption on May 12, 1999 (ADAMS Accession No. ML090750111). The scram function of the control rod drive system controls reactivity changes during abnormal operational transients to ensure that specified acceptable fuel design
-2 limits are not exceeded. SR 3.1.4.1 currently requires each control rod to be scram time tested prior to exceeding 40 percent rated thermal power (RTP) if any fuel movement in the reactor pressure vessel occurs. As a result, even if only one bundle in the reactor core is moved, all of the control rods in the reactor core are required to be tested.
The licensee proposed to delete this requirement and add a new requirement to SR 3.1.4.4.
SR 3.1.4.4 will require affected control rods to be scram time testing prior to exceeding 40 percent RTP (Le., fuel movement within the affected core cell). This is acceptable since control rod scram times are most likely to be affected by fuel movement within the affected core cell. In addition, SR 3.1.4.1 will still require that every control rod be scram time tested prior to exceeding 40 percent RTP if the reactor has been shut down for greater than or equal to 120 days. The NRC staff has concluded that the licensee's proposal is consistent with the intent of TSTF-222, Revision 1. SR 3.1.4.1 and SR 3.1.4.4 assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Therefore, 10 CFR 50.36(c)(3) will continue to be met. Based on the above, the NRC staff concludes that the proposed change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (76 FR 9824). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable insurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Kristy Bucholtz Date of issuance:
May 19, 2011
May 19, 2011 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
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO.1 - ISSUANCE OF AMENDMENT RE: LICENSE AMENDMENT TO MODIFY TECHNICAL SPECIFICATION 3.1.4, "CONTROL ROD SCRAM TIMES," TO INCORPORATE TECHNICAL SPECIFICATION TASK FORCE (TSTF) CHANGE TRAVELER TSTF-222 (TAC NO. ME5192)
Dear Mr. Bezilla:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 157 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No.1. This amendment revises the technical specifications in response to your application dated December 15, 2010 (Agencywide Documents Access and Management System Accession No. ML103630423).
This license amendment modifies the requirements for testing control rod scram times following fuel movement within the reactor pressure vessel by incorporating the NRC-approved TSTF-222-A, Revision 1.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRA!
Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 157 to NPF-58
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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- Memo Dated NRR-058 OFFICE DORULPL3-2/PM DORULPL3-2/LA DIRS/ITSB/BC NAME MMahoney SRohrer REIliott DATE 5/18/11 4/18/11
- 2/17/11 OFFICE OGC-NLO DSS/SRXB/BC DORULPL3-2/BC NAME RHarper AUlses JZimmerman DATE 5/16/11 5/6111 5/19/11 OFFICIAL RECORD COpy