ML19318A654
| ML19318A654 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/19/1980 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19318A653 | List: |
| References | |
| NUDOCS 8006230593 | |
| Download: ML19318A654 (4) | |
Text
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PORTLAND CENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LICllT COMPANY TROJAN NUCLEAR PLANT Operating License NPF-1 Docket 50-344 License Change Application 59, Revisi,a 2 This Revision 2 to License Change Applicacion (LCA) 59 is submitted in support of Licensee's request to modify Appendix A of Facility Operating License NPF-1 by addition of a new Technical Specific.ition for the alter-nate shutdown capability, a change in Technical Specification 6.2.2.a to reflect the minimum shift crew for safe shutdown, and modifications in the Trojan Technical Specifications to include the latest revision to the Standard Technical Specifications on fire protection.
PORTLAND CENERAL ELECTRIC COMPANY By e
C. Coodwin, Jr. /
Assistant Vice President Thermal Plant Operation and Maintenance Subscribed and sworn to before me this 19th day of June 1980.
s h,tiry Public of Oregon
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My Commission Expires:
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4 LCA 59, RIvision 2 Pega 1 of 3 LICENSE CHANGE APPLICATION 59 1.
Modify the below listed Technical Specifications as shown in Attachment A:
a.
Specifications 3.3.3.7, Action a.,
4.3.3.7.1 and Table 3.3-10.
b.
Specifications 3.7.8.1, Action c.,
and 4.7.8.1.2.c.
c.
Specifications 3.7.8.3, Action a.,
and 4.7.8.3.b.2.
d.
Specification 3.7.9, Actr'ns a., b. and c.
2.
Add new Technical Specifications 3.3.3.8 (Limiting Condition for Operation), 4.3.3.8 (Surveillance ?equirements), and 3/4.3.3.8 (Bases for Decouple Switches) as shuen in Attachment A for Decouple Switches.
3.
Modify Technical Specification 6.2.2a to read as follows:
a) "Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
The minimum shift crew necessary for safe shutdown is fi ve. "
b) Modify Table 6.2-1 as shown in Attachment A.
4.
Add the following to Technical Specification 6.2.2.f:
" Fire brigade composition may be less than the minimum require-ments for a period of time not to exceed 2 hrs. in order to accomod' te unexpected absence of on-duty members provided a
immediate action is taken to restore the fire brigade composition to within the minimum requirements of S."
o REASON FOR CHANGE 1.
The NRC letter of March 2'.,
380 requested PGE to submit the neces-sary Technical Specifications for the Alternate Shutdown System (Decouple Switches).
New Technical Specifications 3.3.3.8 and 4.3.3.8 are provided in response to this request.
2.
The NRC letter of March 25, 1980 requested a change to Technical Specification 6.2.2f that identifies the specific number of opera-tors excluded from the fire brigade in order to safely shutdown the Plant. In lieu of modifying Technical Specification 6.2.2f, Technical Specification 6.2.2a and Table 6.2-1 have been changed.
3.
Subsequent discussions indicate that the NRC position regarding decouple switches is that the associated equipment is inoperable
4 LCA 59, Ravision 2 Pegs 2 of 3 if the. decouple' switch.is in the decoupled position and the appli-cability should refer to the-Limiting Condition for Operation for g
the appropriate equipment.
.4.
The NRC has' forwarded -the latest revision to Westinghouse Standard Technical Specifications on fire protection and suggested that the
. Trojan Technical Specifications be modified to incorporate some of the more recent requirements.
1 SAFETY EVALUATION I
This LCA has been reviewed, evaluated and determined.to not constitute l
an unreviewed~ safety question. No new accidents are created and the probability and consequences of accidents previously considered remained unchanged or are reduced.
No environmental effects or impact result from this LCA.
~ Electrical control cables of both redundant divisions are located in the
-cable spreading room (CSR).
There is a remote possibility that should a i
fire occur in this area, if not promptly. suppressed, both redundant safety divisions could be affected due to heat generation.
Additionally, the i
vertical arrangement of some cable trays could increase the burning rate and flame propagation.
Loss of various cables could result in loss of control of safe shutdown equipment.
Since the current sprinkler system i
is actuated by fusible elements rated at 165*F, a cable fire could smol-
~
der and burn for an extended period of time before the temperature of the sprinkler head reaches 165'F.
Also, because of the vertical distance from the lower cable trays in the CSR to the existing sprinkler system, i
a fire of considerable size could develop before system actuation.
i To adequately protect the' safe shutdown cables in the CSR, an alternate shutdown system'will be provided. The alternate shutdown system is described in the NRC Safety Evaluation Report (SER) dated March' 22, 1978 and' consists of decouple switches.
The decouple switches allo'w the control cables to specific equipment required for safe shutdown of the Plant that pass through the CSR to be isolated from the equipment and allow local operation of the equipment.
.Certain control room cabinets also contain redundant safe shutdown com-1 ponents.
A fire in one of these cabinets could cause the loss of control of certain safe shutdown equipment.
Fire detectors are already being installed in individual control room cabinets with redundant components.
~
In addition, the decouple switches will isblate the control room circuits from the specific equipment and allow local operation of the equipment to obtain safe shutdown.
Since potential fires will not prevent safe shutdown, that is,-the neces-sary equipment can be operated from~outside the control room and CSR, an unreviewed safety question does'not exist.
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LCA 59, Revision 2 Psga 3 of 3
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AMENDMENT CLASS This license' change has been determined to be a Class III Amendment in accordance with the criteria of 10 CFR 70.22.
This change involves a single issue with specific NRC positions already existing and met by this amendment.- This change has been deemed to not involve a signifi-cant saftey hazard.
Action on this issue was initiated prior to the effective date of 10 CFR 170; therefore, no fee is required. Although a fee of $4,000 was submitted for this license change on April 19, 1980, the NRC is requested to transfer that fee to LCA 61, submitted May 12, 1980.
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KM/ag/4sa6A19