ML20005E167
| ML20005E167 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/20/1989 |
| From: | Walt T PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20005E165 | List: |
| References | |
| NUDOCS 9001040014 | |
| Download: ML20005E167 (3) | |
Text
.--
j L.:
^ [*;
. * -L.
')
)
PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND 4
PACIFIC POWER-&-LIGHT' COMPANY
'J I
Operating License NPF-1 Docket 50-344 License Change Application 188 This License Change Application requests modifications.to Operating License NPF-1 for the Trojan Nuclear Plant to revise the Trojan Technical Specifications to correct an error contained in Figure 3.4-2, " Reactor i
Coolant System Pressure - Temperature Limits Versus 60'F/ Hour Heatup Rate - Criticality Limit and Hydrostatic Test Limit".
PORTLAND GENERAL ELECTRIC COMPANY By Y. D. Walt General Manager Technical Functions Subscribed and sworn to before me this 20th day of December 1989.
OMyCommission d
4 Notary Public of Op%gon
- wd [ /IN/
/
9001040014 891220 PDR ADOCK 05000344 p
= - -
m-
=
7 - 4 t
4 i
49 LCA 188 Attachment A Page 1 of 2 Description of Change A revision is proposed to Trojan Technical Specifications (TTS)
Figure 3.4-2, which shows Reactor Coolant System (RCS)
Pressure-Temperature Limits for Heatup Rates to 60*F per Hour.
Reason for Channe A corrected curve was received from Westinghouse which showed that the original heatup curve contained in WCAP-10861, " Analysis of Capsulo X
' from Portland General Electric Company Trojan Reactor Vessel Radiation Surveillance Program", June 1985 was in error.
The original curve shows the notch region at 160'F while the corrected curve shows this region at 150*F.
Since this'heatup curve is contained in TTS Figure 3.4-2, a revision to the TTS is desirable. Because the present heatup curve is conservative.(1.e., it is slightly more restrictive) relative to the corrected curve, its continued use will not impact Plant safety.
However, to ensure consistency with the revised curve received from Westinghouse, we propose to make the change.
Determination of Significant Hazards Considerations In accordance with the requirements of Title 10, Code of Federal Regula-tions, Part 50.92, this License Change Request is judged to involve no significant hazards based upon the following information:
.1.
Does the proposed license change involve a significant increase in the probability or consequences of an accident?
l The heatup curve limits the pressure-temperature operation of the l
RCS to ensure the ability of the reactor vessel to-resist fracture.
The proposed change to the curve will not impact any accident since proper assurance of adequate fracture toughness of the reactor vessel is provided by complying with the heatup curve. Using the correct heatup curve will ensure compliance and thus cannot increase the probability or consequences of an accident.
2.
Does the proposed license change create the possibility of a new or different kind of accident from any accident previously analyzed?
The proposed change corrects an error only and will not create a new accident nor contribute to any equipment failure.
3.
Does the proposed license change involve a significant reduction in a margin of safety?
Because the change is administrative only (i.e., it corrects an error), it does not impact the safety margin.
La ;
s' j
J LCA 188 Attachment A Page 2 of 2 In the March 6, 1986 Federal Register, the NRC published a list of examples of amendments that are not likely to involve a significant i
hazards consideration.
Example (1) from this list _ states:
"A purely administrative change to technical specifications:
For example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change.in nomenclature."
Because the proposed change corrects an error and is thus similar to Example (1), it does not involve a significant hazards consideration.
1 Safety / Environmental Evaluation Safety and environmental evaluations were performed as required by Title 10. Code of Federal Regulations, Part 50 and the TTS.
The review determined that the proposed change does not create an unreviewed safety question, nor does it create an unreviewed environmental question.
Schedule Considerations It is requested that the effective date of the amendment be 30 days after issuance by the NRC.
DB0/bsh 3919W.1289
..