ML20078P351
| ML20078P351 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/19/1983 |
| 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 | |
| ML20078P354 | List: |
| References | |
| DPR-50-A-089 NUDOCS 8311080006 | |
| Download: ML20078P351 (5) | |
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UNITED STATES
[ j'i., { j NUCLEAR REGULATORY COMMISSION
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPOPATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.89 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nucleaf Co'rporation, et al (the licensees), dated January 21, 1983, comolies'with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; 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 Comission's regulations and all applicable requirements have been satisfied.
8311080006 831019 PDR ADOCK 05000289 P
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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. DPR-50 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
John' F. Stolz, Chief i
Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: Octobe r 19, 1983 I
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ATTACHMENT TO LICENSE AMENDMENT NO.89 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Rsmove Pages Insert Pages 3-37 3-37 3-37a 3-37a 9
2
l 3.5.3 ENGINEERED SAFEGUARDS PROTECTION SYSTEM ACTUATION SETPOINTS Acolicabilitv:
This specification applies to the engineered safeguards protection system actuation setpoints.
Objective:
To provide for automatic initiation of the engineered safeguards protection system in the event of a breach of Reactor Coolant System integrity.
Specification:
3.5.3.1 The engineered safeguards protection system actuation setpoints and permissible bypasses shall be as follows:
Initiatine Signal Function Setpoint High Reactor Building Rearcor Building Spray
< 30 psig Pressure (1)
Reactor Building Isola-
< 30 psig tion High-Pressure Injection
< 4 psig Low-Pressure Injection
< 4 psig Start Reactor Building Cooling & Reactor Building Isolation
< 4 psig*
Low Reactor Coolant High Pressure Injection 1 1600(2) and System Pressure 2, 500(3) psig Low Pressure Injection 1 1600(2) and 1 500(3) psig Reactor Building Isolation 1 1600 psig (2) 4.16 kv I.S. Buses Undervoltage Relays Degraded Voltage (5)
Switch to On ite Power Source and load shedding 3595 volts (4)
Degraded grid timer 10 see-(5)
Loss of voltage Switch to Onsite Pcuer Source and load shedding 2400 Volts (6)
Loss of voltage timer 1.5 sec (7)
(1) May be bypassed for reactor building leak rate test.
(2) May be bypassed below 1775 psig on decreasing pressure and is automatically reinstated bef ore 1800 psig on increasing pressure.
(3) May be bypassed below 925 psig on decreasing pressure and is autcmatically reinstated before exceeding 950 psig on increasing pressure.
L Amendment No. 70, 73 /$, 89 3-37
(4) Minimum allowed setting is 3560 v. Maximum allowed setting is 3650 v.
(5) Minimum allowed time is 8 sec. maximum allowed time is 12 sec.
(6) Minimu= allowed setting is 2200 volts, maximum allcwed setting is 2860 volts.
(7) Minimum allowed time is (1.0) second, maxi =um allowed time is (2.0) secends.
- For Hot Functional Testing prior to Cycle 5 criticality, the 4 psig Reacter Building isolation signal is not required for Nuclear Service Closed Cycle Cooling water, Intermediate cooling water and Reactor Coolant Pump seal injection (return line only).
Remote Manual and 30 psig Reactor Building isolation signals are required if the 4 psig signal is not operable for these lines.
Bases Hich Reactor Building Pressure The basis for the 30 psig and 4 psig setpoints for the high pressure signal is to establish a setting which would be reached in adequate time in the event
- f a LOCA, cover'a spectrum of break sizes and yet be far enough above normal o
operation maximum internal pressures to prevent spurious initiation.
Low Reactor Coolant System Pressure The basis for the 1600 and 500 psig low reactor coolant pressure setpoint for high and low pressure injection initiation is to establish a value which is high enough such that protection is provided for the entire spectrum to break sizes and is far enough below normal operating pressure to prevent spurious initiation.
Bypass of HPI below 1775 psig and LPI below 925 psig, prevents ECCS actuation during normal system cooldown.
4.16 KV ES Bus Undervoltsce Relays The basis for the degraded grid voltage relay setpoint is to protect the safety related electrical equipment frem loss of function in the event of a sustained degraded voltage condition on the offsite power system.
The timer setting prevents spurious transfer to the onsite source for transient conditiens.
The loss of voltage relay and tLmers detect loss of offsite poeer condition and initiate transfer te the onsite source with ninimal time delay.
Amendment No. /Q, /3, /8,89 3-37a
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