ML19276E466
| ML19276E466 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/12/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19276E465 | List: |
| References | |
| NUDOCS 7903140201 | |
| Download: ML19276E466 (7) | |
Text
w J
Oi b
UNilED STATES p
e "*
- 4 NUCLEAR REGULATORY COMMISSION j
TL
._ j WASHINGTON, D. C. 20555 i
o
\\..v.../
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 Amendment No. 36 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, Pacific Power and Light Company (the licensee) dated March 13, 1978 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 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.
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 racility License No. NPF-1 is hereby amended to read as follows:
'l903140201
. "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 36, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in para-graph 2.C.(10) below."
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
- n A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 12, 1979
ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 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. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 7-5 3/4 7-18
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
One feedwater pump capable of being powered by an OPERASLE a.
diesel with 3. 450 gallons of fuel in its day tank, and b.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY _: MODES 1, 2 and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore the inoperable pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
At least once per 31 days by:
a.
1.
Verifying that the diesel-driven pump Starts and develops a discharge pressure of.1580 psig at 1200 RPM engine 3
speed on recirculation flow, and Verifying that the steam turbine-driven pump starts and 2.
develops a discharge pressure of 3.1580 psig at 4560 RPM on recirculation flow when the secondary steam pressure is > 800 psig.
Pump OPERABILITY may be determined at lower pressures in MODES 2 or 3 by verifying that the steam turbine-driven pump starts and develops a discharge 3,1470 psig on recirculation flow when the pressure of secondary steam pressure is > 275 psig; however, OPERABILITY at 4560 RPM shall be verified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after secondary steam pressure is increased above 800 psig.
TROJAN-UNIT 1 3/4 7-5 Amendment No. 36
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.
Verifying that each pump operates for at least 15 minutes.
4.
Cycling each testable power operated or automatic valve in the flow path through at least one complete cycle of full travel.
5.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months, during shutdown, by:
1.
Cycling each power operated (excluding automatic) valve in the flow path that is not testable during plant operation, through at least once complete cycle of full travel.
2.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.
3.
Verifying that each pump starts automatically upon receipt of a safety injection test signal.
4.7.1.2.2 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying the fuel level in its day tank, 2.
Verifying that a sample of diesel fuel from its fuel tank is within the acceptable limits specified in Table 1 of ASTM D975-68 when checked for viscosity, water and sediment, and 3.
Verifying the diesel starts from ambient condition and operates for 1 15 minutes.
b.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to a inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, and 2.
Verifying'the diesel and pump operate for 1 60 minutes.
TROJAN.-UNIT 1 3/4 7-6
PLANT SYSTEMS 3/4.7.5 ULTIMATE riEAT SINK LIMITING CONDITION FOR OPERATION 3. 7. 5.1 The cooling tower basin shall be OPERABLE with:
6 A minimum contained water volume of 3 x 10 gallons, and a.
b.
An average water temperature of < 95 F.
l APPLICABILITY: MODES 1, 2, 3 and 4.
_ ACTION:
With the requirements of the above specification not satisfied, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4. 7. 5.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their limits.
TROJAN-UNIT 1 3/4 7-17 Amendment No.17
PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.
AFPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one control room emergency ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.6.1 Each control room emergency ventilation system shall be demon-strated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating a.
ficw through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the preheaters on and maintains the control room air temperature l
< 110 F.-
TROJAN-UNIT 1 3/4 7-18 Amendment No. 36
.