ML20070D728
| ML20070D728 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/25/1991 |
| 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 | |
| ML20070D730 | List: |
| References | |
| DPR-50-A-159 NUDOCS 9103010123 | |
| Download: ML20070D728 (5) | |
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UNITED STATES j',lg e
NUCLEAR REGULATORY COMMISSION
.c WASHINGTON, o. C. 70555
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.159 License No. OPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amenament by GPU Nuclear Corporation, et al.
(the licensee) dated November 20, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as i*' ended (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.
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91030101;t) 910225 PDR ADOCK 0S000289 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 Doerating License No.
OPR-50 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159, 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 its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
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I/ ohp F. Stolz, Director
/ Pr# ject Directorate I-Ofvision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ol Issuance: Feb ruary 25, 1991 i
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l ATTACHMENT TO LICENSE AMENOMENT NO.159 FACILITY OPERATING LICENSE NO. OPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
9emove Insert 3-37 3-37 3-37a 3-37a
3.5.3 ENGlNEERED SAFEGUARDS PROTECT!ON SYSTEM ACTUAT10N SETPOINTS Applicability:
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:
Initiating Signal Function tetpoint High Reactor Building Reactor Building Spray f 30 psig Pressure (1)
Reactor Building Isolation < 30 psig High-Pressure Injection 3 4 psig low-Pressure Injection f 4 psig Start Reactor Building Cooling & Reactor Building Isolation f 4 psig Low Reactor Coolant High Pressure Injection 2 1600(2) and System Pressure 2 500(3) psig Low Pressure Injection 2 1600(2) and 2 500(3) psig Reactor Building Isolation 2 1600 psig(2) 4.16 kv E.S. Buses Undervoltage Relays Degraded Voltage Switch to Onsite Power i
Source and load shedding 3760 volts (4)
I Degraded voltage timer 10 sec (5) l Loss of voltage Switch to Onsite Power 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 before 1800 psig on increasing pressure.
l (3) May be bypassed below 925 psig on decreasing pressure and is l
automatically reinstated before exceeding 950 psig on increasing pressure.
3-37 Amendment No. 70, 73, 78, 89, 149' *
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(4) Minimum allowed setting is 3740 v. Maximum allowed setting is 3773 v.
(5) Minimum allowed time is 8 sec. maximum allow)d time is 12 sec.
(6) Minimum allowed setting is 2200 volts, maximum allowed setting is 2860 volts (7) Minimum allowed time is 1.0 second, maximum allowed time is 2.0 seconds.
Bases-High Reactor Building Pressure The basis for the 30 psig and 4 psig setpoints for the high pressure signal is to establish a sett',ng which would be reached in adequate time in the event of a LOCA, cover a spectrum of break sizes and yet be far enough above normal operation maximum internal pressures to prevent spurious initiation (Reference 1).
Low Reactor Coolant System Pressure 1
The basis for-the 1600 and 500 psig low reactor coolant pressura setpoint for high and low pressure irdection 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 (References 1 and 2).
4.16 KV-ES Bus Undervoltage Relays The basis for the degraded grid voltage relay setpoint is to protect the safety related electrical equipment from 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 conditions.
-The loss of voltage relay and timers detect loss of offsite power condition and initiate transfer to the onsite source with minimal time delay.
.The minimum and maximum allowed settings for the degraded voltage setpoint are based on a relay tolerance of -0.53%, +0.35% and is to be considered an "as-left" setting.
References (1)-UFSAR,-Table.7.1-3 i
(2) UFSAR, Section 14.1.2.10
" Steam Generator Tube Failure" l
3-37a j
Amendment No. 70, 73, 78, 89, 149, 157, 159
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