ML20209C648

Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev

ML20209C648
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/06/1999
From:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20209C651	List: ML20209C648 ML20209C653
References
VPN-053-99, VPN-53-99, NUDOCS 9907120159
Download: ML20209C648 (6)

Text

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Trojan Nudear Plant i i ri< c.-, y 71760 Columbia River Hwy Rainier OR 97048 (50m556-sn3 July 6,1999 VPN-053-99 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Trojan Nuclear Plant Defueled Safety Analysis Reoort. Revision 8 The enclosure to this letter provides one original and ten copies of Revision 8 to the Trojan Nuclear Plant Defueled Safety Analysis Report (DSAR). Revision 8 includes changes to the DSAR since the last submittal. The attachment to this letter includes a brief description of each change included in this revision. Text changes are identified in the DSAR by margin bars adjacent to the chang and revision numbers at the page bottom. Each copy of Revision 8 is accompanied by a set ofinstructions for insertion into the DSAR.

I hereby certify that Revision 8 accurately presents changes made since Revision 7 neces' ary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirements.

Sincerely, et4 A t hen M. Quennoz Vice President, Nuclear and Thermal Operations

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Attachment Enclosure c: D. Stewart-Smith, OOE Director, NRC, NMS L. H. Thonus, NRC, NRR hW 9907120159 990706 PDR ADOCK 05000344 W pog Connecting People, Power and Possibilities .

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s r Attachment to VPN-053-99 July 6,1999 Page 1 of 3 ,

Description of Changes 4

The following changes to the DSAR implement changes pursuant to the 10 CFR 50.59 process.

Changes are categorized by the implementing Licensing Document Change Request (LDCR) number.

. LDCR 98-050 Changes are incorporated into Sections 1.2.3,5.2-1,5.3-2, and 5.5.2.2.~ Sections 5.2.1,5.5.2.2.4, and Figure 5.2-1 are deleted. The changes reflect deactivation

, of the vent collection header and associated piping and components per Defueled Plant Modification Request (DPMR)97-007, Detailed Construction Package (DCP) 20.

The Vent Collection Header System is no longer required to vent the tank / sump air spaces due to significant reduction in quantities ofliquid waste processed by the Liquid Radioactive Waste System. Remaining liquid waste is primarily from draining and washing equipment for removal.

LDCR 98-053  : Section 4.1.3.1 is changed to remove reference to the Seismic Triaxial Time History Recording System. The System was deactivated by' DPMR 98-007, DCP 3. Deactivation was necessary due to electrical interferences during decommissioning activities in the 45 foot elevation of the Auxiliary and Fuel Buildings.

LDCR 98-054 Section 3.3.4.2 is changed to indicate that water entering the Service Water System can be chlorinated, when necessary, for microbiological control. Prior changes to the Service Water System (performed under DPMR 98-002, DCP 3) eliminated the need for regular periodic chlorination of the Service Water System.

. LDCR 98-055 Section 3.3.7, describing the Makeup Water Treatment System (MWTS), is deleted. The System was deactivated to remove interferences during the Reactor Vessel and Intemals Removal (RVAIR) project. Removal of the demineralized

- water storage tank and associated equipmenticomponents was performed under DPMR 98-015, DCP 9.

LDCR 99-002 Section 3.3.4.2 is changed to reflect that pump P-108C receives power from bus Al only. The alternate power from bus A2 to P-108C was deactivated by DPMR 98-007, DCP 7.

LDCR 99-004 Section 7.1.2.2 is changed to reflect the new title for Manager, Nuclear Regulatory Affairs, due to organizational changes.

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Attachment to VPN-053-99 July 6,1999 Page 2 cf 3 LDCR 99-008 Section 4.2.1 is changed to revise the indicated path for Fuel Building crane movement by the Spent Fuel Pool. Changes result from DPMR 97-012, DCP 6, which moved the electrical limit switch for the crane closer to the Spent Fuel Pool to accommodate Independent Spent Fuel Storage Installation (ISFSI)

Transfer Cask and Fuel basket loading.

1 LDCR 99-009 Sections 5.3.1 and 5.3.2 are changed to indicate deactivation of the Auxiliary  !

and Containment Building sump pumps and floor and equipment drains  !

accomplished under DPMR 99-002, DCP 2. Figure 5.3-1 is also revised to reflect the changes.

LDCR 99-012 Section 1.4.1.15 is changed to indicate that, in regard to criticality accident monitoring,10 CFR 50.68(b) is followed rather than 10 CFR 70.24. Table 3.5-1 l is modified to delete Regulatory Guide 8.5 since its intent is to indicate an acceptable method of compliance with 10 CFR 70.24.

LDCR 99-014 Section 5.4.1 subsection (1) is deleted and Section 5.4.2 is modified to remove j eferences to the filter handling vehicle. The filter handling vehicle was disassembled and removed. The vehicle is no longer needed due to removal of all filters in the filter pits and concrete plugs for the filter pits.

LDCR 99-018 Section 5.5.2.2.1 is changed to indicate that Process Radiation Monitor (PRM) 1 is no longer available to sample Containment. Containment atmosphere sample valves for PRM-1 were electrically deactivated by DPMR 98-007, DCP 20.

LDCR 99-020 Sections 1.2,1.5, 2.1.1.2, 2.1.2.2, 3.0, 3.3.1, 3.6, 4.2.1, 4.5, 6.2, and 6.4 are reused to reflect NRC approval of License Change Applications (LCAs)237 and 246 for spent fuel cask loading and unloading in the Fuel Building and LCA 242 for removal of the ISFSI area from the site area licensed under 10 CFR 50.

LDCR 99-026 Item 4 of Section 4.2.1.1 and Figure 4.2-2 are deleted. These changes omit outdated information and incorporate design changes for safe load paths consistent with LCA 237 for ISFSI fuel loading.

LDCR 99-028 Sections 2.1.2,2.2.1, and 2.2.3 are revised to reflect current rail line operator, Portland & Western Railroad. PGE's agreement with Portland & Western Railroad functions in place of the prior agreement with Burlington Northern.

Reference Sections 2.6,3.6,4.5,5.9, and 6.4 are reformatted for consistency.

LDCR 99-035 Section 4.1.3.1 is revised to credit seismic monitor SR6340B in place of SR6340F for ground level monitoring.

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Attachment to VPN-053-99 July 6,1999

, Pane 3 of 3 LDCR 99-036 Section 3.3.4.2 is revised to delete references to the Service Water System strainer and booster pumps per DPMR 98-002, DCP,3.

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LGD-084-99 To: Distribution From: - L G. Dusek Date: July 6,1999

Subject:

Transmittal of Revision 8 to the Trojan Nuclear Plant Defueled Safety Amlysis Reoort Enclosed is your controlled copy of Revision 8 to the Trojan Nuclear Plant Defueled Safety Analysis Report. Please acknowledge receipt of your copy by completing the lower portion of j

this transmittal and returning it to the location given below.

{

l LGD/CKC Enclosure 7/6/99

, ACKNOWIFDGMENT Revision 8-Trojan Nuclear Plant Defueled Safety Analysis Report I hereby acknowledge receipt of Controlled Copy Number (s) of the subject o

document. All changes have been made in accordance with the instructions, and superseded pages have been destroyed.

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Signature of Copy Holder Date l Return to

Pat Schaffran, TCB-3/ Licensing

, Trojan Nuclear Plant 71760 Columbia River Highway  ;

Rainier, Oregon 97048 l

1 TROJAN NUCLEAR PLANT j Defueled Safety Analysis Reoort. Revision 8 l

The follovdng information is furnished as a guide for the insertion of new sheets for Revision 8 into the Trojan Nuclear Plant Defue' led $afety Analysis Report. This material is denoted by the use of the revision 3

number in the lower outside corner of the page. Revised pages should be inserted as listed below:

Delete (Front /Back) Insert (Front /Back) i/ii and iii/iv i/ii and iii/iv vii/viii through xi/xii vii/viii through xi/xii xxiii/ xxiv through xxix/ blank ,

xxiii/ xxiv through xxix/ blank 1.2-1/1.2-2 1.2-1/l.2-2 1.4-5/1.4-6 1.4-5/1.4-6 1.5-1/ blank 1.5-1/ blank 2.1-1/2.1-2 through 2.1-11/2.1-12 2.1-1/2.1-2 through 2.1-11/2.1-12 2.2-1/2.2-2 through 2.2 17/2.2-18 2.2-1/2.2-2 through 2.2 17/2.2-18 2.6-1/2.6-2 through 2.6-9/2.6-10 2.6-1/2.6-2 through 2.6-9/2.6-10 3.0-1/ blank 3.0-1/ blank 3.3-1/3.3-2 3.3-1/3.3-2 3.3-9/3.3-10 through 3.3-13/3.3-14 3.3-9/3.3-10 through 3.3-13/3.3-14 3.6-1/3.6-2 and 3.6-3/blar.k 3.6-1/3.6-2 and 3.6-3/ blank Table 3.5-1, Sheets 1/2 through 37/38 Table 3.5-1, Sheets 1 through 35 4.1-3/4.1-4 4.1-3/4.1-4 4.2-1/4.2-2 and 4.2-3/ blank ,

4.2-1/4.2-2 and 4.2-3/ blank 4.5-1/ blank ,.4.5-1/ blank Figure 4.2-2 .

5.2-1/5.2-2 through 5.2-9/ blank 5.2-1/5.2-2 through 5.2-7/ blank 5.3-1/5.3-2 through 5.3-3/5.3-4 5.3-1/5.3-2 and 5.3-3/5.3-4 5.4-1/5,4-2 and 5.4-3/ blank 5.4-1/5.4-2 and 5.4-3/ blank 5.5 3/5.5-4 through 5.5-9/5.5-10 5.5-3/5.5-4 through 5.5-9/ blank 5.9-1/5.9-2 5.9-1/5.9-2 ,

Figure 5.2-1 -----

j Figure 5.3-1 Figure 5.3-1 1

6.2-1/6.2-2 and 6.2-3/ blank 6.2-1/6.2-2 and 6.2-3/ blank 6.4-1/6.4-2 6.4-1/6.4-2 and 6.4-3/ blank 7.1-3/7.1-4 7.1-3/7.1-4 I