ML19309F694
| ML19309F694 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/25/1980 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 TAC-30689, NUDOCS 8004300380 | |
| Download: ML19309F694 (3) | |
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April 25, 1980 Trojan Nuclear Plant Docket 50-344 s
Ldcense NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operatt.ng Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
On April 15, 1980, PGE submitted supplemental information regarding implementation of NUREC-0578 Short-Term Lessons Learned Actions at the Trojan plant. During a subsequent telephone call on April 19, 1980, concerns raised by members of the NRC Staff were satisfactorily resolved and it was concluded that th'e only change necessary to PGE's submittal of April 15 was in nection 2.1.6.a
" Integrity ef Systems outside Containment Likely to Contain Radioactivity". Attached is a copy of the revised Section 2.1.6.a of PGE's submittal of April 15 containing additional clarifications discussed and agreed with by the NRC Staf f.
Areas of changes for additional clarification are denoted by side bars in the Attachment.
Sincerely,
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Mr. Lynn Frank, Director State of Oregon Department of Energy 4 <> 1
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Section 2.1.6.a - Integrity of Systems outside Containment Likely to Conttin Radioactivity The supplemental leak reduction program had been developed at Trojan to reduce leakage from systems outside Containment that would or could contain highly radioactive fluids during a serious transient or accident.
The program consists of periodic leak tests on specified systems to verify system integrity and to identit; leakage. Where possible, the testing will be performed by inspecting potential leakage areas such as flanges, pump seals and valve packing while the system is maintained at operating pressure.
For systems containing gases, the test program will include the use of helium leak tracer by qualified personnel. The sup-plemental leak reduction program will be implemented at refueling cycle inte rval. Weld and piping integrity vill continue to be tested in accordance with the Inservice Inspection Program.
Leakage identified during the test will be properly recorded and a schedule for repair of the source of excess leakage will be established to ensure its timely completion consistent with system operation and the magnitude of the leak.
The acceptance criteria to be applied for leakage will be the design leak rate for individual components within the system in accordance with ALARA criteria.
Systems and/or portions of systems that would contain highly radioactive fluida during a serious transient or accident condition were reviewed for necessity of supplemental leak detection. The criteria used in determin-ing which systems to be included in the supplemental program were:
1.
System or a portion of the system located outside of the Containment.
2.
System likely to contain highly radioactive fluids in the event of a serious transient or accident.
3.
System or a portion of the system required to function during or following an accident or severe transient in i
order to bring the Plant to a safe shutdown condition.
i By applying these criteria, the following systems were included in the leak reduction program:
Chemical and Volume Control System - including letdown, makeup, seal injection, CVCS demineralizers and holdup tanks.
Safety Injection System - flow path from EHR to CVCS charging pump suction via the. safety injection system.
Residual Heat Removal System - all of the system outside of Containment...
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e Containment Spray System - all portions of the system required to recirculate water from the sump.
Radioactive Caseous Waste System - all portions of the system associated with processing the gas from the CVCS holdup tanks.
Reactor Coolant Sampling System - Portions of the sampling system required for post-accident sampling.
Containment Atmospheric Sampling System - Portions of the sampling system required for post-accident sampling.
Systems which need to be tested during Plant shutdown will be leak tested using the supplemental program prior to the startup of cycle 3 in 1980; other systems will be inspected within 1 month of operation time af ter the startup of Cycle 3 in 1980.
Other Plant systems were excluded from the program since they did not meet the three criteria listed above. Examples of those systems excluded are:
Boron Recovery System - not required for safe shutdown of the Plant.
Liquid Radioactive Waste System - not required for safe shutdown of the Plant.
(This system was excluded by the NRC in the NRC letter of clarifications dated October 30, 1979.)
Chemical and Volume Control System - not required for safe shutdown of the Plant.
(That portion of the system isolated and not included in the above list.)
Component Cooling Water System - not containing radioactivity during normal and ar.cident condition. Two pressure boundary must fail before leakage to the environment.
Hydrogen Recombiners - system within Containment.
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