ML20137N909

Application for Amend to License NPF-1,consisting of License Change Application 135,making Miscellaneous Corrections to Tech Specs 4.0.2,4.4.6.1,3.4.9.3 & Table 3.6-1

ML20137N909
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	01/31/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20137N899	List: ML20137N896 ML20137N909 ML20137N935
References
TAC-60618, NUDOCS 8602040287
Download: ML20137N909 (4)

Text

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l PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT COMPANY l

l Operating License NPF-1 Docket 50-344 License Change Application 135 This License Change Application requests modifications to Operating License NPF-1 for the Trojan Nuclear Plant to make miscellaneous corrections to Technical Specifications 4.0.2, 4.4.6.1, 3.4.9.3, and Table 3.6-1.

PORTLAND GENERAL ELECTRIC COMPANY By Bart D. Withers Vice President Nuclear l Subscribed and sworn to before me this 31st day of January 1986.

NotaryPublicofO[on 9MyCommission e

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LCA 135 Page 1 of 3 DESCRIPTION OF CHANGE The following changes are proposed to the Trojan Technical Specifications (TTS) as discussed below and shown in Attachment 1.

REASON FOR CHANGE Page 3/4 0 TTS 4.0.2.b is revised to correct a typographical error.

Page 3/4 4 TTS 4.4.6.1.b is revised to correct an editorial error.

" CALIBRATION TEST" is changed to " CHANNEL CALIBRATION". CALIBRATION TEST is not a defined term in TTS 1.0, whereas CHANNEL CALIBRATION is defined and correctly describes the surveillance performed.

Page 3/4 4-28a - TTS 3.4.9.3 is revised to correct an editorial error.

The correct Reactor Coolant System vent size is 3.40 square inches, not 3 square inches.

Pages 3/4 6-22 through 24 - TTS Table 3.6-1 is revised to delete valve CV-8825. This valve is the RHR hot Icg recirculation valve inside Containment. This valve was inadvertently not deleted from Table 3.6-1 in LCA 124 when Table 3.6-1 underwent a general revision. The basis for not including this valve is that this piping penetration is Type IV.

Type IV penetrations are required for post-Design Basis Event operation.

By definition, Type IV penetrations only require one barrier. This barrier is provided by valve MO-8703 (RHR hot les recirculation outside Containment), which is still included in Table 3.6-1.

TTS Table 3.6-1 is also revised to allow manual valve MD-059 (demineral-ized water washdown) to be periodically opened under administrative control. This is accomplished by referencing the new footnote in Table 3.6-1 which is denoted by ##. Valve MD-059 is opened to provide water to the Containment for fire protection when activities are occur-ring inside containment which pose a fire hazard. The availability of the water is required per TTS 3.7.8.3, " Fire Hose Stations". Administra-tively controlling the opening of valve MD-059 will allow both TTS 3.6.3.1 and 3.7.8.3 to be satisfied.

SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The proposed changes do not increase the probability or consequences of an accident because:

1. The changes to TTS 4.0.2.b, 4.4.6.1.b, and 3.4.9.3 are adminis-trative in that they correct typographical errors and make editorial improvements.

2. The change to TTS Table 3.6-1 which deletes CV-8825 is also a correction since it deletes a valve which was inadvertently not deleted from LCA 124. Valve CV-8825 (RHR hot leg recirculation

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5 LCA 135 page 2 of 3 to SIS test line - inside Containment) is associated with a piping penetration which is Type IV. As discussed in FSAR Section 6.2.4.1 Type IV penetrations are those fluid lines which must remain in service subsequent to a design basis event.

Type IV penetrations are required to have one Containment isola-tion valve. Valve MO-8703 (RHR hot leg recirculation - outside Containment) is the Containment isolation valve, not CV-8825.

3. The change to TTS Table 3.6-1 is administrative since it resolves a conflict between TTS 3.6.3.1, containment Isolation Valves, and TTS 3.7.8.3, Fire Hose Stations. An example of when the conflict may crise is when the Plant is in Mode 4 and work is occurring inside containment for which the availability of water for fire protection is required. Valve MD-059 would be open to make demineralized water available for fire protection inside Containment. However, TTS 3.6.3.1 requires that this valve be closed from a Containment integrity standpoint. Allowing valve MD-059 to be opened under administrative control will allow TTS 3.7.8.3 to be met, while also satisfying TTS 3.6.3.1. A check valve is available inside Containment to isolate Containment and valve MD-059 could be immediately closed if necessary.

The proposed changes do not create a new or different kind of accident because:

1. The changes to TTS 4.0.2.b, 4.4.6.1.b and 3.4.9.3 are adminis-trative in that they correct typographical errors and make editorial improvements.

2. The changes to TTS Table 3.6-1 are not related to creating a new or different kind of accident, but rather, deal with accident mitigation as related to Containment integrity. As previously discussed, Containment integrity is not compromised by this change.

The proposed changes do not result in a reduction in a margin of a safety because:

1. The changes to TTS 4.0.2.b, 4.4.6.1.b, and 3.4.9.3 are adminis-trative in that they correct typographical errors and make editorial improvements.

2. The changes to TTS Table 3.6-1 do not compromise Containment integrity. Therefore, no reduction in the safety provided by the Containment is proposed. From a fire protection standpoint, as related to valve MD-059, with this valve open the availability of fire water inside Containment is assured and, therefore, safety is enhanced.

LCA 135 page 3 of 3 In the April 6, 1983 Federal Register, the NRC published a list of examples of amendments that are not likely to involve a significant hazards consideration. Example No. 1 of that list applies to the changes proposed herein and states:

"A purely administrative change to the technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."

Since the above example is judged to apply to the proposed changes, the proposed changes are deemed not to pose a significant hazard.

SAFETY /FNVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the TTS. This review determined that the proposed changes do not create an unreviewed safety question.

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