ML20034C885
| ML20034C885 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/11/1990 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034C884 | List: |
| References | |
| NUDOCS 9005210040 | |
| Download: ML20034C885 (6) | |
Text
{{#Wiki_filter:, 4,, UNITED STATES e ,[ g NUCLE AR REGULATORY COMMISSION i -5 t WASHING TON, D. C, 20556 4,.....,o l PORTLAND GENERAL ELECTRIC COMPANY [ THE CITY OF EDGENE. OREGON f PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 [ TROJAN NUCLEAR PLANT AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 159 'icense No. NPF-1 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Portland General Electric et al., (the licensee) dated November 13, 1989, I Company, WitF the standards and requirements of the Atomic cneplies 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 appli-cation, the provisions of the Act, and the regulations of- ' i the Comission; l C. Thereisreasonableassurance(1)thattheactivities authorized by this amendment can be conducted without-endangering the health and safety of the public, and 1 (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common 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 51 of the Comission's regulations and all applicable require-ments have been satisfied. i l 9005210040 900521 L PDR ADOCK 05000344 P PDC i i ---,e a
2 2. Accordingly, the license is amended by changes to the Technical l Specifications as indicated in the attachment to this license i 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.159, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions. 3. This license amendment is effective as of the date of its' issuance. FOR THE NUCLEAR REGULATORY COMM:SSION I John T. Larkins, Acting Director Project Directorate V Division of Reactor Projects 111, IV, Y and Special Projects Office of Nuclear Reactor Regulation ~
Attachment:
Changes to the Technical Specifications Date of Issuance: May 11, 1990 G 4 1 l r
-i \\ ~ 't ATTACHMENT TO LICENSE AMENDNENT NO.159 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. Remove Pages Insert Pages -{ 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 B 3/4 7-4 B 3/4 7-4 ,r l 0 d t
j PLANT SYSTEMS '3/4.7.3 CDMDONENT COOLING WATER SYSTEM i LIMITING CONDITION FOR OPERATION k i 3.7.3.1 At least two independent component cooling water (CCW) trains shall be j i OPERABLE. n APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only one CCW train OPERABLE, restore the other train to OPERABLE status within 72 hours or be in COLD SHUTDOWN within the i next 36 hours. + L SURVEILLANCE REOUIREMENTS 4.7.3.1 The CCW System shall be demonstrated OPERABLE: I At least once per 31 days by verifying that occh valve 1 a. (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise 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. At least once per 18 months, during shutdown, by verifying that c. 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. I d. At least once per 18 months, during shutdown, by verifying that valves NO-3294, MO-3296 M0-3300, and'M0-3320 actuate to their correct position on: 1. A Contalyaent isolation signal coincident with a low CCW surge tank level, and 2. A high-high Containment pressure signal. By verifying that each power operated (excluding-automatic) e. valve is OPERABLE when tested pursuant to Specification 4.0.5. 4 t TROJAN-UNIT 1 3/4 7-13 Amendment,No. 7( 72#, IAl, May 11, 1990
l j PLANT SYSTEMS l CDNPONENT COOLING WATER SYSTEM i LIMITING CONDITIDN FOR OPERATION i i 3.f.3.2 At least one component cooling water (CCW) train capable of-supply-ing cooling heter to equipment needed in MODES $ and 6 shall be OPERABLE. APPLICABILITY: MODES $ and 6. l ACTIDN: With less than the required number of CCW trains OPERABLE, declare supported equipment inoperable. .i SURVEILLANCE REQUIREMENTS t 4.7.3.2 At least one CCW train sha1J 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. i t I h 5 ? l l W 4 t 9 1ROJAN-UNll 1 .3/4 7-14 Ameno;.ent No. 7d, Tid, I4I, 159 May 11, 1990
l l PLANT SYSTEMS BASES 3/4.7.3 COMPONENT COOLING WATit SYSitM The OPERA 81LITY of the CCW System ensures that sufficient cool'ing capacity is available for continued operation of safety-related equipment i 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 analyses. i g 3/4.7.4 $[RVICE WATER SYSTEN The OPERABillTY of the service water system ensures that sufficient-cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capattity.of this system, assumin's a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits. 3/4.7.5 ULTIMATE HEAT $1NK i The Columbia River is the ultimate heat sink and ensures that l l suf ficient 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 i 100 hours) cooling water supply to safety related equipment in the event the normal water supply from the intake structure is lost. The required amount of water is adequate to provide normal cooldown of the facility until makeup flow f rom the Columbia River to the cooling tower basin can i be restored. i 1 i l 1 2 1ROJAN-UNil 1 B 3/4 7-4 Amendment No. 128, TW, 4 159 May it, 1990 .}}