ML20203B029

Forwards Rev 5 to Trojan Nuclear Plant Defueled SAR, Including Brief Description of Changes in Rev

ML20203B029
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/26/1997
From:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20203B032	List: ML20203B029 ML20203B034
References
VPN-071-97, VPN-71-97, NUDOCS 9712120312
Download: ML20203B029 (5)

Text

Portland General Electric One World Trade Center 121 SW Sa!nwn Street Portland. OR 97204

-November 26,1997 VPN-071-97 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, DC 20555 Trojan Nuclear Plant Defueled Safety Analysis Report. Revision 5 The enclosure to this letter provides one original and ten copies of Revision 5 to the Trojan Nuclear Plant Defueled Safety Analysis Report (DSAR). Revision 5 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. Changes to each page are identified in the DSAR text by margin bars adjacent to the change and revision numbers at the page bottom. Each copy of Revision 5 is accompanied by a set ofinstructions for insertion into the DSAR.

I hereby certify that Revision 5 accurately presents changes made since Revision 4 necessary to retlect informatica and analyses submitted to the Commission or prepared pursuant to Commission requirements.

Sincerely, yW . . . .

Stephen M. Quennaz Trojan Site Executive p Attachment .2OOOb \

D. Stewart-Smith, OOE

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R. A. Scarano, NRC Region IV -

. M. T. Masnik NRC,gRR ,

i ,, ,

9712120312 971126 P ADOCK 05000344 PDR .

Nat. ural gas. Electricity. Endless possibilities.

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Attachment to VPN-07197 November 26,1997 Page1of3 ,

Description of Changes 1

The following changes to the DSAR implement changes pursuant to the 10 CFR 50.59 process, with the exception of LDCR 97-020, which reflects implementation of an approved License -!

Amendment: .

LDCR 97-002 Change to Figure 3.3 1 to remove unused piping associated with the RIIR and refueling cavity connections to the spent fuel cooling system.

DPMR 96-026 provides positive closures for the piping and allows removal of the unused piping during decommissioning activities.

LDCR 97-003 Change to Figure 5.3 2 to iadicate a generic air supply for the reactor cavity sump pump associated with DPMR 97 003 01. The DPMR isolates ,

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instrument air to containment, and provides for alternative air supply for the sump pump, when needed. -

LDCR 97-004 Section 5.2.2.2 was revised to change the description of the containment l purge exhaust system to indicate the addition of a prefilter. DSAR changes associated with DPMR 96-018-01 include the revision to Figure 5.2.3. Miscellaneous edits were made to Section 6.3.1, Figure 3.3-3,

• Table 4.3 1, and Table 4.1-1.

LDCR 97 005 Changes to Section 3.3.3.2 and Figure 3.3-2 delete references to the component cooling water emergency nitrogen supply, which was deactivated by DPMR 97-006-02. The emergency nitrogen system was no longer required due to srent fuel pool cooling function of the component cooling water system not needing an elevated cover gas pressure to preclude boiling. The emergency nitrogen bottle rack interfered with removing material from the pipe facade during decommissioning activities.

LDCR 97-008 This is an administrative change to Figure 5.2 to make it consistent with the description of the vent collection header system in the body of the DSAR. DPMR 97-007-01 installed caps on piping from active plant -

systems connected to the clean radwaste evaporator, including clean radwaste lines to and from the evaporator, the evaporator vents connected to the vent collection header, and the instrument air line to the evaporator. .

Figure 5.2-1 was modified to eliminate the connection to the vent collection header.

Attachment to VPN-07197 November 26,1997 Page 2 of 3 LDCR 97-009 A radwaste handling / processing area was established in the Condensate Demineralizer Building (now refered to as the Radwaste Processing Building). The work completed by DPMR 97-005-01 is reflected in the DSAR as changes to Sections 5.2,5.4,5.5, and the addition of Section 5.2.4 and Figure 5.2-7.

Section 5.2.4 is new. It describes the Condensate Demineralizer Building's ventilation system and radioactive airbome particulate monitor.

Wording was added to Section 5.5.2.2 to describe the gas monitoring method for the building to include the new effluent path created by the modification. Section 5.5.2.2.5 was added to describe the sampling and monitoring components in the building's ventilation system. Figure 5.2-7 was added to illustrate the buiMing's ventilation system.

Minor editorial changes were made to indicate work completion.

1.DCR 97 015 These chan;;es to Section 4.2.1 clarify that routine sorting of non spent fuel assembly radioactive material (filters, debris, and other material placed in the pool for shielding and housekeeping purposes) stored in the spent fuel pool does not constitute a fuel handling activity. This is an administrative change to separate these activities from prohibited " fuel handling activities," such as the movement of fuel assemblies into the Containment Building.

LDCR 97-017 Section 6.1 was changed to clarify that the intent of he section is to describe the bounding accident scenarios for liquid and gaseous radioactive releases, and that equipment described may be deactivated and removed, consistent with the Decommissioning Plan described process controls.

LDCR 97-018 Changes Section 3.3.4.2 and Figure 3.3 3 to specify two service water booster pumps and deletes references to two loops of service water makeup to the spent fuel pool. This change is consistent with the existing text of Section 3.3.4.2 that "only one service water booster pump is required to provide 100 percent of the loop flow requirement." These changes result from the completion of DPMR 96-013-01.

Attachment to VPN 071-97 November 26,1997 Page 3 of 3 1.DCR 97 019 Changes, based on the completion of DPMR 96-028-01, to Sections 3.1, 3.2,4.1, and 4.2. The changes include references to the impact of removing a spent fuel storage rack to facilitate spent fuel pool floor cleaning and currecting the number of cells available.

LDCR 97-020 Changes to the DSAR based on the implementation of License Amendment 196 (approved by the NRC, May 19,1997). The movement of spent fuel shipping casks into the Fuel Building prohibition was removed from Sections 3 and 4. PGE-1037," Trojan Nuclear Plant Spent Fuel Storage Rack Replacement Report," was removed from the list of material incorporated into the DSAR by reference (Section 1.5), due to the topical report being a historical document.

LDCR 97 025 F!gure 3.3-1 was revised to remove connections not addressed or described in the narrative of the DSAR. The connections were removed by DPMR 97-006-05.

TROJAN NUCLEAR PLANT Defueled Safety Analysis Report. Revision 5 The following information is furnished as a guide for the insertion of new sheets for Revision 5 into the Trojan Nuclear Plant Defueled Safety Analysis Report. This material is denoted by the use of the revision number in the lower outside corner of the page. Revised pages should be inserted as listed below:

lasert (Front /Ilack) Delete (Front /Back) i/ii through xxix/ blank i/ii through xxix/ blank 1.5-1/ blank 1.5-1/ blank 3.1-5/3.1-6 and 3.1-7/3.1-8 3.1-5/3.1-6 and 3.1-7/3.1-8 3.2-3/3.2-4 through 3.2-7/3.28 3.2-3/3.2-4 through 3.2-7/3.28 3.2-35/3.2-36 through 3.2-41/ blank 3.2 35/3.2-36 through 3.2-41/ blank 3.3-1/3.3-2 3.31/3.3-2 3.3 9/3.3-10 through 3.3-19/ blank 3.3-9/3.3 10 through 3.3-19/ blank

--- 3.45/3.4-6 3.6-1/3.6-2 3.6 1/3.6-2 Figures 3.3 i/ blank through 3.3-3/ blank Figures 3.3-1/ blank through 3.3-3/ blank 4.1-1/4.1-2 through 4.1-5/4.1-6 4.1-1/4.1-2 through 4.1-5/4.1-6 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 Table 4.1-1/ blank, Page 1 Table 4.1-1/ blank, Page i Table 4.1-1/ blank, Page 2 Table 4.1-1/ blank, Page 2 Table 4.3-1/ blank Table 4.3-1/ blank 5.2-3/5.2-4 5.2-3/5.2-4 5.2-7/5.28 5.2-7/ blank 5.4-3/5.4-4 5.4-3/5.4-4 5.5-5/5.5-6 through 5.5-9/5.5 10 5.5-5/5.5-6 through 5.5-9/5.5-10 5.6-7/5.6-8 5 6-7/5.6-8 Figure 5.2-1/ blank Figure 5.2-1/5.2-2 Figure 5.2-2/ blank ---

Figure 5.2-3/ blank Figure 5.2-3/5.2-4 Figure 5.2-4/ blank ---

Figure 5.2-7/biank ---

Figure 5.3 l/ blank 5.3-1/5.3-2 Figure 5.3-2/ blank ---

6.1-1/6.1-2 6.1-1/6.1-2 6.31/6.32 6.3-I /6.3-2