ML20206B571
| ML20206B571 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/02/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B568 | List: |
| References | |
| NUDOCS 8704090240 | |
| Download: ML20206B571 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION t.
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WASHINGTON, D. C. 20555
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN' NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendirent No. 126 License No. NPF-1 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Portland General Electric Company, et al., (the licensee) dated January 31, 1986, as supplemented Hiiy76,1986 and February 26, 1987, complies with the standard 3 and requirements of the Atomic Energy Act of 1954, as amended
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(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 (1) 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 emendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 8704090240 870402 PDR ADOCK 0500 4
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2.
Accordinaly, 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. NPF-1 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.126, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of its issuance.
F0 THE NUCLE R
TORY COMMISSION 4
gl, ect PWR Project Directorat d o. 3 Division of PWR Licens ng A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 2, 1987 I
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k UNITED STATES NUCLEAR REGULATORY COMMISS!ON o
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ATTACHMENT TO LICENSE AMENDMENT NO.126
-T0 FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 l
i Revise Appendix A as follows:
Remove Pages Insert Pages TS 3/4 4-13 TS 3/4 4-13 3/4 4-28a 3/4 4-28a 3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24 s
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.
Containment sump inventory and containment air cooler condensate inventory (if being used)-performance of CHANNEL CALIBRATION at l
least once per 18 months, 8
I 4
TROJAN-UNIT 1 3/4 4-13 Amend. No. 12f
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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS 1'
LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems i
shall be OPERA 8LE:
a.
Two power-operated relief valves (PORVs) with lift settings of.440 psig and 490 psig, or b.
A reactor coolant system vent of 13.40 square inches.
APPLICABILITY: When the temperature of one or more of the RCS cold legs is 1 290*F*.
ACTION:
a.
With one PORV inoperable, either restore the inoperable PQRE to OPERABLE status within 7 days or depressurize and vent the RCS through a 1 3.40 square inch vent (s) within the l
next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; unintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.
b.
With both PORVs inoperable, depressurize and vent the RCS -
through a 1 3.40 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain l
the RCS in a vented condition until both PORVs have been restored to OPERABLE status, c.
In the event either the PORVs or the RCS vent (s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant 4
to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient, and any corrective action necessary to prevent recurrence.
d.
The provisions of Specification 3.0.4 are not applicable.
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- A maximum of one safety injection pump shall be OPERABLE.
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I TROJAN-UNIT 1 3/4 4-28a Amendment No. 75,126
TABLE 3.6-1 CONTAINMENT ISOLATION VALVES
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TESTABLE DURING ISOLATION TIME 5
VALVE NUMBER FUNCTION PLANT OPERATION
_, (seconds)
E.
Non-automatic Power Operated Valves Continued CV 8881#
SIS discharge Train "A" - inside yes N.A.
MO 8802Af SIS discharge Train "A" - outside no N.A.
CV 8824#
SIS discharge Train "B" - inside yes N.A.
MO 8802B#
SIS discharge Train "B" - outside no N.A.
F.
Manual Valves 8090A*
(RCS) Deadweight Tester - outside yes N.A.
80908*
(RCS) Deadweight Tester - outside yes N.A.
i SF080 Refueling cavity recirculation -
w" inside N.A.
SF046 Refueling cavity recirculation -
outside N.A.
SF073 Refueling cavity drain - inside N.A.
SF074 Refueling cavity drain - outside N.A.
SF063 Refueling cavity skinuning -
inside N.A.
SF062 Refueling cavity skinsning -
outside N.A.
MD059##
Demin. water wash down -
l outside N.A.
FWO79#-FWO86#
Feedwater Line Drains no N.A.
g Main Steam Line Drains no N.A.
M5013#-MS016#*
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g TABLE 3.6-1 E
g CONTAINNENT ISOLATION VALVES E
C TESTABLE DURING ISOLATION TIME
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VALVE NUMBER FUNCTION PLANT OPERATION (seconds)
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G.
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8047 PRT N2 Supply - inside no N.A.
8046 PNU Water to Press.
a!
Relief Tank - inside no N.A.
4 8190 RCP Seal Water Rrn. - inside no N.A.
l 8968 N2 to Accumulators - inside no N.A.
Check valve Demin. Water to Washdown Sta. - inside no N.A.
j Check valve RCDT N2 Supply - inside no N.A.
4 Check valve downstream of CV 4470 Service Air - inside i
Check valve downstream no N.A.
i of CV 4471 Instrument Air - inside no N.A.
May be opened on an intermittent basis under administrative control.
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- The Containment purge supply and exhaust valves shall be made inoperable (electric power or air supplies removed from the?r respective operators) during Podes 1 through 4.
- The Hydrogen veut supply and exhaust valves shall be normally closed, and opened only when and for the duration of time actua11y necessary.
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- Not subject to Type C leakage tests.
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- Nay be opened under administrative control when personnel fire protection required.
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