ML19289C551
| ML19289C551 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/09/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7901170323 | |
| Download: ML19289C551 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMisslON y*
3 Ii*l. j WASHINJToN, D. C. 20555
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January 9, 1979 Docket No. 50-344 Mr. Charles Goodwin, Jr.
Assistant Vice President Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204
Dear Mr. Goodwin:
RE: OVERPRESSURE PROTECTION TECHNICAL SPECIFICATIONS In our earlier discussions with you regarding your overpressure protection system, we indicated that Technical Specifications would be necessary to ensure the operability of the system and to require the disabling of any equipment, such as charging pumps or safety injection pumps. Such specifications will ensure that the Appendix G limits for your reactor vessel will not be exceeded in the event of a pressure transient, assuming a single failure.
The enclosed model Technical Specifications are being provided for your guidance in preparing your submittal for the Trojan Nuclear Plant. You are requested to submit your proposed Technical Specifications within 60 days of receipt of this letter.
This license amendment to incorporate the proposed Technical Specifications has been determined to be a Class III Amendment.
You should submit the appropriate fee.
Sincerely,
%$O$&
A.Sdhwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Enclosure:
Model Technical Specifications cc: w/ enclosure See next page 790117 652 7 Y
Portland General Electric Company January 9, 1979 cc:
Mr. H. H. Phillips Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Mr. J. L. Frewing, Manager Generation Licensing and Analysis Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Columbia County Courthouse Law Library, Circuit Court Room St. Helens, Oregon 97501 Director, Oregon Department of Energy Labor & Industries Building, Rm. 111 Salem, Oregon 97310 Richard M. Sandvik, Esquire Counsel for Oregon Energy Facility Siting Counsel and Oregon Department of Energy 500 Pacific Building 520 SW Yamhill Portland, Oregon 97204 Michael Malmrose U. S. Nuclear Regulatory Comission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048
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E! ERGEi:CY CORE C0CLI!!G SYSTEMS, ECCS SUBSYSTEMS
_T_3yg <350 F LIIiITIrlG CONDITICil FOR OPERATIO!!
A maximum of one centrifugal charging pump and,one' high pressure 3.5.3 injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is <(275)*F.
SURVEILLAI!CE RE0VIREMEllTS 4.5.3 All charging pumps anri safety injection pumps except those other-wise required to be OPERABLE shall be demonstrated inoperable at least once per 12 hcurs whenever the temperature of one er more of the RCS cold legs is <(275) F by verifying the motor circuit breakers have been recoved from tneir electrical power supply circuits.
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EMERGENCY CORE COOLING SYSTEMS BASES The limitation for a maximum of one high pressure safety injection pump to be OPERABLE and the Surveillance Requirement to verify all high pressure safety injection pumps except the required OPERABLE pump to be inoperable below (275)*F provides assurance that a mass addition' pressure transient can be relieved by the operation of a single PORV.
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDIT!9N FOR OPERATION 3.1. 2. 3 One charging pump in the boron injection flow pat'h required by Specification (3.1.2.1) shall be OPERABLE and capable'of being powered from an OPERABLE emergency bus.
APPLICABILITY: MODES 5 and 6.
SURVEILLANCE REQUIREMENTS 7
-l 4.1. 2. 3 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at lea-t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verifying that the motor circuit breakers have been removed from their electrical power supply circuits.
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3/4.1 REACTI'/IT'I CC:!T:CL SYSTE-!S CASES 3/4.1.1 BORATION SYSTEMS 1
The 1imitatio:. for a.7,axi=um of one contrifug:1 charging pump to be
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OPERABLE and the Surveillance Requirement to verify all charging pum::s except the required CPERASLE puma to be inoperabla belcw (275)*F provides i
assurance that a mass addition pressure transient can be relieved by
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the operation of a single PORV.
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' REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure. protection systems shall be OPERABLE:
Two power operated relief valves (PORVs) with a lift setting a.
of 1 (450) psig, or b.
A reactor coolant system vent of > (
)squareinches.
APPLICABILITY: Wh'en the temperature of one or more of the RCS cold legs is 1 (275}'F.
ACTION:
a.
With one PORV inoperable, either restore the inoperable PCRV f to OPERABLE status within 7 days or depressurize and vent the RCS through a (
) square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORys have been restored to OPERASLE status.
b.
Vith both PORys inoperable, depressurize and vent the RCS through a (
) 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 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 Ccmmission pursuant to Specification 6.9.2 within 30 days. The report shall describe the c.ircumstances initiating the transient, the effsct cf the P,0RVs or vent (s) on the transient and any correctiYe action necessary to prevent recurrence.
d.
The provisions of Specificati~on 3.0.4 are act applicable.
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. REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
a.-
Performance of a CHANNEL FUNCTIONAL TEST.on the PORV actuaticn channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERASLE.
b.
Performance of a CdANNEL CALIBRATION on the PORV actuation channel at least once per 18 months.
- c.. ' Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being ussd for overpressure pro:eccien.
d.
. Testing in accordance with the inservice test requirements for i
ASME Category C values as specified in Section XI of the ASME. Boiler and Pressure Vessel Code 1974 Edition, and Adderda through Winter 1975.
4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent (s) is being used for over' pressure prot.ection.
- Except when the vent pathway is provided with a valve which is lccked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
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A reactor coolant pump shall not be started with one or more of the RCS co'id leg temperat.ure <(275)*F unless 1) the pressurizer water
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volume is less than
-cubic feet or 2) the secondary water temperature of each steam generator is less than
'F above each of the RCS cold leg temperatures.
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I REACTOR C00LAtlT SYSTEM BASES The OPERABILITY of two PORVs or an RCS vent opening of greater than
(
) square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to ~10 CFR Part 50 when one or more of the RCS cold legs are <(275)*F.
Either PORV has adequate reli'eving capability to protect th~e RCS from overpressurization when the transient is limited to either (1) the start of an idle RCS with the secondary water temperature ai the steam generator <(
)*F above the RCS cold leg temperature or (2) the start of a HPSI pump and its injection into a w:ter solid RCS.
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