ML20091B348
| ML20091B348 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/20/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20091B351 | List: |
| References | |
| DPR-50-A-162 NUDOCS 9106030121 | |
| Download: ML20091B348 (5) | |
Text
{{#Wiki_filter:p " " %,1 UNITED STATES 0 NUCLEAR REGULATORY COMMISSION j g u VVASHING TON. D. C. 20555 e '44.....$ METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. DPR-50 1. The Nuclear Regulatory Commission (the Cor: mission) has found that: A. The application for amendment by GPU Nuclear Corporation, et al. (the licensee) dated March 25, 1991, 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; l 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 l by this amendment can be cor. ducted without endangering the health and safety of the public, and (ii) that such activities will be I conducted in compliance with the Cammission's regulations; I D. The issuance of this amendment will not be inimical to the common i 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 Commissicn's regulations and all applicable requirements have been satisfied. l l 9106030121 910520 PDR ADOCK 05000289 P PDR
1 ! l 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 f acility Operating License No. DPR-50 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.162, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications. 3. This license amendnient is effective as of its date of issuance, to be implemented within 30 days of issuance. FOR THE NUCLEAR REGULATORY COMMISSION / Joh r
- olz, rector Pr ject Directorate 1
' vision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 20, 1991
A \\ A TACHMENT TO LICENSE AMENDMENT NO. 162 FACILITY OPERATING LICENSE NO. DPR-50 i DOCKET N0. 50-289 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment i. umber and contains vertical lities indicating the area of change. Removc Insert 3-25 3-25 4-Sa 4-Sa
-. ~. - I i 3.4 DECAY HEAT REMOVAL CAPABI'J11 6pplicability Applies to the operating status of systems and components that function to remove decay heat when one or more fuel bundles are located in the reactor vessel. Obiective To define the conditions necessary to assure continuous capability of decay heat removal." Specification 3.4.1 Reactor Coolant System temperature greater than 2$0'F. 3.4.1.1 With the Reactor Coolant temperature greater than 250'F, three independent ErW pumps and associated flow paths shall be OPERABLE ** withs a. Two EFW pumps, each capable of being powered from an OPERABLE emergency bus, and one EFW pump capable of being powered from an OPERABLE steam supply system. (1) With one pump or flow path inoporable, restore the inoperable pump or flow path to OPERABLE status within 72 hours or be in COLD SHUTDOWN within the next 12 hours. (2) With more than one ETW pump or flow path inoperable, reatore the inoperable pumps or flow paths to OPERABLE status or be suberitical within 1 hour, in at least HOT SHUTDOWN within the next 6 hours, and in COLD SHUTDOWN within the following 6 hours, b. Four of the six turbine bypass valves OPERABLE. With more than two turbine bypass valves inoperable, restore operability of at least four turbine bypass valves within 72 hours. c. The condensate storage tanks (CSTs) OPERABLE with a minimum of 150,000 gallons of condensate available in each CST. (1) With a CST inoperable, restore the CST to operability within 72 hours or be in at least HOT SHUTDOWN within the next 6 hours, and 00LD SHUTDOWN within the next 30 hours. (2) With more than one CST inoperable, restore the inoperable CST to OPERABLE status or be suberitical within 1 hour, in at least HOT SHUTDOWN within the next 6 hours, and in COLD SHUTDOWN within the following 6 hours.
- These requirements supplement the requirements of Sections 3.1.1.1.c, 3.1.1.2, 3.3.1, and 3.8.3.
- HSPS operability is specified in Section 3.5.1, 3-25 Amendment No.
4, 78, 98, 119, 124, 162
E TABLE 4.1-1 (Continued) O I CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS - 28. Radiation Monitoring Systems
- W(1)(3)
M(3) Q(2) (1) Using the installed check source when background is less than twice the expected ? y increase in cpm which would result from the check source alone. Background readings g greater than this value are sufficient in o themselves to show that the monitor is 8 functioning. ? (?) Except area gamma radiation monitors RM-GS, g RM-G6, RM-G7 and RM-G21 which are located p in the Reactor Building. When purging is permitted per T.S. 3.6, RM-G5 and RM-G21 9 will be calibrated quarterly. If purging is not permitted per T.S. 3.6, RM-GS and g RM-G21 shall be calibrated at the next p scheduled reactor shutdown following the N g' quarter in which calibration would normally be due. RM-G6 and RM-G7, which are in high radiation areas shall be calibrated at the next scheduled reactor shutdown following the quarter in which calibration is due, if a shutdown during the quarter does not occur. l (3) Surveillances are required to be performed only when containment integrity is required. This applies to monitors which initiate containment isolation only. 29. High and Low pressure N/A N/A R Injection Systems: Flow Channels
- Does not include the monitors covered under Specification 3.5.5.2 and 4.1.3 or Specifications 3.21.1,3.2i.2 and 4.21.1, 4.21.2.
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