ML20149H171

Forwards Rev 1 to Trojan Nuclear Plant Defueled Sar

ML20149H171
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/10/1994
From:	Quennoz S, Yundt C PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20149H176	List: ML20149H171 ML20149H177
References
VPN-047-94, VPN-47-94, NUDOCS 9411180145
Download: ML20149H171 (2)

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Portland General Electric bompany l Trojan Nuclear Plant I 71760 Columbia River liwy Rainier, Oregon 97048 November 10,1994 l (503) 556-3713 VPN-047-94 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission i Attn: Document Control Desk Washington, DC 20555 e

Dear Sirs:

Defueled Safety Analysis Report. Revision 1 This letter transm',s, one original and ten conformed copies of Revision 1 to the Trojan Nuclear Plant Drfueled Safety Analysis Report (DSAR). Attachment 1 provides a brief description of changes made to the DSAR in this revision. Changes are marked for identification in the DSAR text by a revision bar.

. Portland General Electric Company (PGE) certifies that Revision 1 accurately represents changes made since the previous submittal, necessary to reflect the information and analyses submitted to the Commission or prepared pursuant to Commission requirements, and descriptions of changes made to the facility and procedures described in the DSAR. Each copy of Revision 1 is accompanica " a set of instructions for insertion into the DSAR.

Sincerely,

( N4 C. E.'Yundt for Stephen M. Quennoz Trojan Site Executive Attachment c: L. J. Callan, NRC Region IV C. L. Cain, NRC Region IV S. J. Collins, NRC Region IV D. Stewart-Smith, ODOE (w/o attachments)

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PDR ADOCK 05000344 P PDR

. Document Control Desk November 10,1994 VPN-047-94 Attachment 1 Page1 ofI DEFUELED SAFETY ANALYSIS REPORT (DSAR)

IDENTIFICATION OF AMENDMENT CHANGES The following list provides a synopsis of DSAR revisions. These changes have been evaluated and determined not to involve an unreviewed safety question as required by Title 10 to the Code of Federal Regulations, Part 50.59.

1. LDCR 93-085 Revises DSAR Table 3.2-5 to correct elevation given for Spent Fuel Pool piping siphon breakers. Minor typographic correction to DSAR Table 3.2-4 (

2. LDCR 94-005 Modifies description of Area Radiation Monitors in the DSAR Section 5.6.1.3 to be consistent with current approved system deactivation plans.

3. LDCR 94-006 Revises DSAR Table 3.1-3 to reflect removal of the Hydrogen Storage Tmks from the facility as a result of approved system deactivation plans.

4. LDCR 94-007 Updates the DSAR Section 3.4.2.1.5 for the Emergency Diesel Generator functions description to reflect current capabilities for the system based on the defueled plant requirements.

5. LDCR 94-013 Revises DSAR Figure 3.3-1 for Spent Fuel Cooling and Demineralizer System to add siphon breaker holes to Fuel Transfer Canal and Cask Load Pit supply lines.

6. LDCR 94-021 Provides clarification in Table 3.5-1 of conformance to Regulatory Guide 1.33, " Quality Assurance Program Requirements" with respect to independent verifications as described in ANSI N18.7-1976.

7. LDCR 94-027 Revises DSAR Figure 3.3-1 for Spent Fuel Cooling and Demineralizer System to indicate existing siphon breaker hole in the system cooling water return line.

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