ML20217Q728
| ML20217Q728 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/27/1997 |
| From: | Eaton R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q730 | List: |
| References | |
| NUDOCS 9709030333 | |
| Download: ML20217Q728 (5) | |
Text
- -
p
\\
UNITED STATES NU3 LEAR RE2ULATeRY CEMMISSIDN
.t cash 1'3f cN. @.C. M4001 g...+
HETROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & llGHT 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. 203 License No. DPR 50 1.
The Nuclear Regulatory Commission (the Commission or NRC) has found that:
A.
The application for amendment by GPU Nuclear Corporation.-et al.
(the licensee) dated April 21, 1997, as supplemented July 17.
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 I:
B.
The facility will operate in conformity with the application, the
]rovisions 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.
D A
O 89 P
4 2
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:
(2)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 203, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordanc6 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 1ya/$IY oridl B. E ton, Acting Director Project Directorate I 3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to tha Technical Specifications Date of Issuance:
August 27, 1997 m._.__.._._......--.
~
ATTACHMENT TO LICENSE AMENDMENT NO. 203 FACILITY OPERATING LICENSE NO. OPR 50 DOCKET NO. 50 289 Replace the following Sages of the Appendix A Technical Specifications, with the attached-pages.
T1e revised pages are identified b contain vertical lines indicating the areas of change. y Amendment number and Remove Insert 3 21 3-21 4 41 4 41
3.3 EMERGENCY CORE COOLING. REACTOR BUILDING EMERGENCY COOLING AND REACTOR BUILDING SPRAY SYSTEMS Applicabijily; Applies to the operating status cf the emergency core cooling, reactor building emergency cooling, and reactor building spray systems.
Objective; To define the conditions necessary to assure immediate availability of the emergency f
core cooling, reacto. ouilding emergency cooling and reactor building spray systems.
Specification:
3.3.1 The reactor shall not be made critical unless the following conditions are met:
3.3.1.1 Inlection Systems The borated water storage tank shall contain a minimum of 350,000 gallons of water n.
having a minimum concentration of 2,500 ppm boron at a temperature not less than 40'F. Specification 3.0.1 applies.
b.
Two makeup pumps are operable in the engineered safeguards mode powered from independent essential buses. Specification 3.0.1 applies.
Two decay heat removal pumps are operable. Speci0 cation 3.0.1 applies.
c.
d.
Two decay heat removal coolers and their cooling water supplies are operable. (See Specification 3.3.1.4) Specification 3.0.1 applies.
Two BWST level instrument channels are operable.
e.
f, The two reactor building sump isolation valves (DH.V-6A/B) shall be remote-manually operable. Specification 3.0.1 applies.
3.3.1.2 Core Floodine System Two core flooding tanks each containing 940 30 ff of borated water at l
a.
600 i_25 psig shall be available. Specification 3.0.1 applies.
b.
Core flooding tank baron concentration shall not be less than 2,270 ppm boron.
The electncally operated discharge valves from the core flood tank will be assured c,
open by administrative control and position indication lamps on the engineered safeguards status panel. Respective breakers for these valves shall be open and conspicuously marked. Specification 3.0.1 applies.
d.
One core flood tank pressure instrumentation channel and one core flood tank level instrumentation channel per tank shall be operable.
3 21 Amendment No.21,98, /M, 203
4.5.3 EMERGENCY CORE COOLING SYSTEM l '.'
Applicability:
Applies to periodic testing requirement for emergency core cooling systems.
Objectivc:
To verify that the emergency core cooling systems are operable.
Specificatimn 4.5.2.1 liigh Pressure injection During each refueling interval and following maintenance or modification a.
that affects system flow characteristics, system pumps a td system high point vents shall be vented, and a system test shall be conducti d to demonstrate that the system is operable.
The makeup pump and its required supporting auxiliaries will be started l
manually by the operator and a test signal will be applied to the high pressure injection (HP1) valves MU V 16A/B/C/D to demonstrate actuation of the high pressure injection system for emergency core cooling operation.
b.
The test will be considered satisfactory if the valves have completed their travel and the makeup pumps are running as evidenced by the control board l component operating lights. Minimum acceptable injection flow must be greater than or equal to 431 spm per HPl pump when pump discharge 1ressure is 600 psig or greater (the pressure between the pump and flow j
imiting device) and when the RCS pressure is equal to or less than 600 psig.
Testing which requires HPl flow through MU V-16A/B/C/D shall be c.
conducted only under either of the following conditions:
1)
T avg shall be greater than 332 'F.
2)
Head of the Reactor Vessel shall be removed.
l 4.5.2.2 Low Pressure injection During each refueling period and following maintenance or modification that a.
affects system flow characteristics, system pumps and high point vents shall be vented, and a system test shall be conducted to demonstrate that the system is operable. The auxiliaries required for low pressure injection are all included in the emergency loading sequence specified in 4.5.1.
b.
The test will be considered satisfactory if the decay heat pumps listed in 4.5.1.lb have been successfully started and the decay heat injection valves and the decay heat supply valves have completed their travel as evidenced by the control board component operating lights. Flow shall be verified to be equal to or Ereater than the flow assumed in the Safety Analysis for the single corresponding RCS pressure used in the test.
4-41 Amendment No.19, 57, f S,- MN 203 4
' ~ - ' - -