ML20199C043
| ML20199C043 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/07/1997 |
| From: | Pickett D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199C045 | List: |
| References | |
| NUDOCS 9711190197 | |
| Download: ML20199C043 (5) | |
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t UNITED STATES
,g NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D.C. 30046 4001 J
'59.....,e THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
1 DOCKET NO. 50 440 PERRY NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.91 License No. NPF-58
- 1. _ The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by The Cleveland Electric Il Nminating Company. Centerior Service Company. Duquesne Light Ccmpany. Ohio Edison Company. OES Nuclear. Inc., Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated October 24, 1996, as supplemented June 16 and October 2. 1997, 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 1:
B.
The facility will cperate 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 Comission'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 Ca nissicn's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amendec 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:
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(2) Technical Soecifications j
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B as revised through Amendment No. 91. are hereby. incorporated into this license.
The Cleveland Electric Illuminating 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 implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m _. k V fd o
Douglas V. Pickett Senior Project Manager
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Project Directorate !!! 3
- Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7, 1997 E
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1 ATTACHMENT TO LICENSE AMENDMENT NO.91 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following 3 ages of the Appendix "A" Technical Specifications with the attached pages.
T1e revised pages are identified by Amendment number and contains vertical lines indicating the area of change.
Remo/e Insert 2.0-1 2.0-1 5.0 18 5.0 18
i SLs 2.0 2.0 SAFETY LlHITS (SLs) 2.1 ^5'us 2.1.1 Reactor Core SLs P
2.1.1.1 With the reactor steam dome pressure < 785 ps10 or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure = 785 psig and core flow = 10% rated core flow
......................-N0TE-----------------
Only applicable for Cycle 7 operation.
MCPR shall be = 1.09 for two recirculation loop operation or = 1.10 for single recirculation loop operation.
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 SL 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.
1 2.2.3 Within-24 hours.-notify the plant manager and the corporate o
executive responsible for overall plant nuclear safety.
(continued)
- PERRY-UNIT.1
. 2,0-1 Amendment No.46h, 91 4
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Reporting Requirements 5.6 5.6 Reporting Requirements l
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 i
limits shall be those >reviously reviewed and aporoved by i
the NRC in NEDE-24011-)-A General Electric Stan'ard d
Application for Reactor Fuel.
(The approved revision at the i
time reload analyses are performed shall be identified in the COLR.)*
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.
- For Cycle 7. as approved in the NRC Safety Evaluation dated November 7, 1997.-
PERRY - UNIT 1 5.0-18 Amendment No f9r 91; J