ML20154A111

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Amend 141 to License NPF-1,revising Tech Spec Section 3/4.7.3, Component Cooling Water Sys to Be Consistent W/ split-train Operation
ML20154A111
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/03/1988
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154A110 List:
References
NUDOCS 8805130145
Download: ML20154A111 (6)
v • d • e


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/ 'o E ,, UNITED STATES E\ e NUCLEAR REGULATORY COMMISSION

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENCMENT TO FACILITY OPERATING LICENSE Amendment No. 141 License No. NPF-1

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated February t,,1988 complies with the italidards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amenonent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8805130145 000503 DR ADOCK 050 44 l

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2. Accordingly, the license is amended by char:ges to .the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.141, are hereby incorporated in the license. The licerisee shall operate the facility in accordance with the Technical Specifica-tions, except where etherwise stated in specific license corditions.

3. This license anendment is effective as cf the date of its issuance.

FOR THE NUCLEAR REGULATORY CCFNISSION i

George W. Knighton, Director ,

Project Directorate V '

Division of Reactor Projects - III, I IV, V and Special Projects

Attachment:

Changes to the Technical l Specifications Date of Issuance: May 3, 1988 1

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i May 3, 1988 ATTACHMENT TO LICENSE AMENDHENT tl0. _

TO FACILITY OPERATING LICEf;SE NO. NPF-1 DOCKET NO. 50-344 Pevise Appendix A as follows:

Pemove Paces Insert Pages 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 B3/4 7-4 B3/4 7-4 i

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PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water (CCW) loops shall be OPERABLE with one train isolated from Seismic Category II loads. The spare CCW pump shall be OPERABLE.  ;

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the spare pump inoperable, restore the spare pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. l With only one CCW train and spare pump OPERABLE, restore the other train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the nut 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE RE0VIREMENTS 4.7.3.1 The CCW System shall be demonstrated OPERABLE: )

a. At least once per 31 days by verifying that each valve l (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise i secured in position, is in its correct position.
b. By verifying that each CCW pump is OPERABLE when tested pursuant to Specification 4.0.5.
c. At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety related equipment, except those valves in Specification 4.7.3.1.d. actuates to its correct position on a Containment isolation signal,
d. At least once per 18 months, during shutdown, by verifying that valves MO-3294, MO-3296, MO-3300, and M0-3320 actuate to their
correct position on
1. A Containment isolation signal coincident with a low CCW surge tank level, and
2. A high-high Containe:nt pressure signal,
e. By verifying that each power operated (excluding automatic) valve is OPERABLE when tested pursuant to Specification 4.0.5.
f. At least once per 31 days by verifying that either CV-3304 and CV-32BB, or CV-3303 and CV-3287, are closed.
g. At least once per 92 days by verifying that power can be supplied i to the spare CCW pump from both buses. l TROJAN-UNIT 1 3/4 7-13 Amendment No. 7#, lid,141 5/3/88 l

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PLANT SYSTEMS COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.2 At least two component cooling water (CCW) trains capable of supply-ing cooling water to equipment needed in MODES 5 and 6, or at least one train and the spare CCW pump, shall be OPERABLE.

APPLICABILITY: MODES 5 ano 6.

ACTION:

With less than the required number of CCW trains OPERABLE, declare supported equipment inoperable.

With only one CCW train OPERABLE and the spare pump inoperable, declare supported equipment inoperable.

SURVEILLANCE REQUIREMENTS 4.7.3.2 At least two CCW trains or one train and the spare CCW pump, shall be demonstrated OPERABLE by verifying that necessary components (the portion necessary to support equipment which is required to be OPERABLE in the applicable MODES above) are OPERABLE when tested pursuant to Specification 4.0.5.

TROJAN-UNIT 1 3/4 7 14 Amendment No. 74. Tid,141 1 5/3/88

PLANT SYSTEMS BASES 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the CCW System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during nornal and accident conditions. The redundant cooling capacity of this system, assuming a singic failure, is consistent with the assumptions used in the accident analyses.

The OPERABILITY of the CCW System with one train isolated f rom Seismic Category 11 loads ensures that sufficient cooling capacity is available for continued operation of safety-related equipment following a seismic event. The GPERABILITY of the spare CCW pump ensures the availability of a CCW loop even with a single-failure concurrent with a seismic event.

Operation in Modes 1 through 4 is pennitted with one CCW train inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the spare CCW pump is OPERABLE.

During this 72-hour time period, the OPERABLE CCW train should not be isolated from Seismic Category 11 loads to ensure a continuous supply of CCW cooling to the reactor coolant pumps. The spare CCW pump is considered OPERABLE provided Surveillance Requirements 4.7.3.1.b and 4.7.3.1.g have been met.

3/4.7.4 SERVICE WATER SYSTEM s

The OPERABILITY of the service water system er.sures that sufficient cooiing capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.

3/4.7.5 ULTIMATE HEAT SINK The Columbia River is the ultimate heat sink and ensures that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on cooling tower basin minimum water level and maximum temperature are based on providing an adequate (approximately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />) cooling water supply to safety related equipment in the event j the nornal water supply f rom the intake structure is lost. The required j amount of water is adequate to provide nornal cooldown of the facility until makeup flow from the Columbia River to the cooling tower basin can be restored. 1 i

TROJAN-UNIT 1 B 3/4 7-4 Amendment No. 720, 141 5/3/88 l

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