ML20205D686
| ML20205D686 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/26/1999 |
| From: | Pickett D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205D690 | List: |
| References | |
| NUDOCS 9904020277 | |
| Download: ML20205D686 (5) | |
Text
e patero o
UNITED STATES
- f.
j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20066 0001 o
%,*****y FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-58 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee, formerly The Cleveland Electric illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc.,
Pennsylvania Power Company, and Toledo Edison Company) dated October 27, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as a' mended (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.
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:
9904020277 990326 PDR ADOCK 05000440 P
(2) Technical Soecificatioqs The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 104 are hereby incorporated into this license. The FirstEnergy Nuclear Operating Company 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 issuance and shall be impleme'nted not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION T r -h V @
Douglas V. Pickett, Senior Project Manager Project Di.ectorate lil-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 26, 1999 i
i
~
ATTACHMENT TO LICENSE AMENDMENT NO,104 l
FACILITY OPERATING LICENSE NO. NPF-58 i
DOCKET NO. 50-440 i
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain verticallines indicating the crea of change.
Remove Insert 2.0-1 2.0-1 5.0-18 5.0-18 1
I i
1 8
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow
< 10% rated core flow:
THERMAL POWER shall be s.25% RTP 2.1.1.2-With the reactor steam dome pressure 2 785 psig and core. flow 2 10% rated core flow:
HCPR shall be 21.09 for two recirculation loop operation or 21.11 for single recirculation loop operation.
l 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure St Reactor steam dome pressure shall be s.1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs: and 2.2.2.2 Insert all insertable control rods, i
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate executive.
responsible for overall plant nuclear safety.
(continued)
PERRY - UNIT 1 2.0-1 Amendment No.104
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core Ooeratino Limits Reoort (COLR)
(continued) 4.
LC0 3.3.1.1 RPS Instrumentation (SR 3.3.1.1.14):
b.
The analytical methods used to determine the core operating
)
limits shall be those )reviously reviewed and approved by the NRC in NEDE-24011-)-A. General Electric Standard Application for Reactor Fuel.
(The approved revision at the j
time reload analyses are performed shall be identified in the COLR.)
l c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits. Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM. transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR. including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Soecial Reoorts Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
The following Special Reports shall be submitted.
a.
Violations of the requirements of the fire protection program described in the USAR which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported via the Licensee Event Report system.
I PERRY - UNIT 1 5.0-18 Aiedelt No.104 l