ML20247P146

Forwards Amend 10 to FSAR for Trojan Nuclear Plant.Amend Includes Effects of Changes Made in Facility Procedures as Described in 820720 FSAR & Revised by Amends 1-9 & Safety Evaluations Performed by Util

ML20247P146
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/31/1989
From:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247P149	List: ML20247P146
References
NUDOCS 8908040049
Download: ML20247P146 (5)

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, aa m - mesi YM Mbl%uW Da tid W. Cockfield Vice President, Nuclear 1

July 31, 1989 Trojan Maclear Plant Docket 50-344 License NPF-1 U. S. Nuclear Regulatory Commissien j Attn: Document Control Desk Wasitington DC 20555

Dear Sir:

Final, safety Analysis Report. Amendment 10 In accordance with Title 10, Code of Federal Regulations, Part 50.71(e),

one original and ten conformed copies of this letter and its attachments are submitted in support of Amendment 10 to the Trojan Nuclear Plant Final Safety Analysis Eeport (FSAR). This amendment includes the effects of: (a) changes anade in the facility or procedures as described in the FSAR submitted on July 20, 1982 and revised by Amendments 1 throur,h.9 and (b) safety evaluations. performed by portland General Electric Company (PGE), either in support of requested license amendments or in support of conclusions that changes.did not involve an unreviewed safety question.

Administrative and editorial changes have been included, as well as technical corrections and clarifications.

The FSAR is organized consistently with the format of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, NUF"<:--0800 (July 1981) . Each copy of Amendment 10 is accompanied by a set of instructions for inserting it into the FSAR. The replacement pages contain " change bars", i.e. , vertical lines in the margin adjacent to the portion actually changed, and each replacement ic labeled

" Amendment 10 (July 1989)".

r fDY b 44 K PDC 1 O S W SaWon Street. Pomand Ore;po 972M

Portland General ElectricConwavy Document Control Desk July 31, 1989 Eale 2 The attachmeni. identifies the changes due to analyses submitted to the NRC or prepared pursuant to NRC requirements and the changes made under provisions of Title 10, code of Federal Regulations, Part 50.59. Other major sources of amend.nent information are also identified.

Sincerely, O

Attachment i

c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. David Stewatc-Smith State of Oregon Departmerit of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Pinnt Subscribed and sworn to before me this 31st day of July 1989.

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.i Trojan' tuclear Plcnt' Document Control Dask Docket 50-344- July 31, 1989 License NPF-1 Attachment Page 1 of 3 3

FINAL SAFETY ANitLYSIS REPORT IDENTIFICATION OF AMENDMENT 10 CHANGES A. Plant'Declan Changes Federal regulations-[ Title 10, Code.of Federal Regulations. Part 50.59 (10 CFR 50.59)] and the Trojan Facility Operating License NPF-1 allow changes to be made to the facility as described'in the Safety Analysis

-Report.:and tests or experiments to be conducted which arc not described in the Safety Analysis Report, without prior Nuclear Regulatory Commis-

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sion (NRC) approval, unless the' proposed change, test, or expe'-iment involves a change in-the Technical Specifications incorporated in the license or an unreviewed safety question. .The following faci)1ty change was evaluated and determined not to involve an unrevirwed safety question.

Plant Design Change 83-052 modified the Steam Generator Blowdown System

.(SCBS). The scope of this modification involved interfaces with the following plant systems: the SCBS, the Condensate and Feedwater

System, the Heater and Miscellaneous Drains System, the Extraction Steam System, the Service Water System, the Turbine Building Drains and Sumps System, the Clean Radwaste System, the Dirty Radwaste System, the Solid Radwaste System, the Primary Makeup Water System, the Radiation Monitoring System, the Spent Fuel Pool Cooling and Domineralizer System, and the Process Sampling System.

This modification to the SGBS increases the maximum system flow capecity from 50 gpm to 100 gpm per steam generator (measured at steam generator outlet conditions), and provides for. heat recovery from the blowdown flashed steam through Feedwater Heater E-103B. Additionally, this modification provides for two Liquid Radwaste System (LRS) ion exchangers dedicated to processing dirty and clean liquid radwaste.

The SGBS lon exchangers will no longer be the means for treating liquid radwaste, but will now'be used for continuous processing of steam generator blowdown liquid condensate to the condenser or to the discharge and dilution structure;'this will improve secondary water chemistry contro1 and will improve liquid radwaste processing

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o flexibility.

This modification installs the following:

1. Replacement SGBS Containment isolation valves with fully environmentally qualified operators.

2. Replacement SGBS piping outside the Reactor Containment Building.

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Trojan Nuclear plant Document Control Desk July 31, 1989 Docket 50-344 License NPF-1 Attachment page 2 of 3

3. A replacement, larger capacity, and improved-design SGBS flash tank with a moisture separator.

4. New flash steam piping from the SGBS tank to the main condenser and to Feedwater Heater E-103B.

5. A new main condenser penetration and internal steam sparger (in the "A" condenser neck, designed and installed via the condenser refurbishment during the 1987 Outage per RDC 83-031).

6. A replacement full-capacity SGBS tank pump.

7. A replacement larger-capacity SGBS tank liquid condensate heat exchanger.

8. New independent discharge flow piping (separate from liquid radwaste) to the condenser and to the discharge and dilu-tion structure.

9. A new atmospheric vent line.

10. A new SGBS tank relief stack to vent above the Turbine Building.

11. Replacement flow and level control valves.

12. Replacement and new instrumentation controls and alarms.

13. A new SGBS control panel in the Turbine Building.

14. A new SGBS building to house the SBGS tank, heat exchanger, pump, and associated valves, piping, and instruments.

15. An improved personnel barrier at the south wall of the Main l

Steam Support Structure (required due to the height and location of the new SGBS building),

l' 16. New LRS ion exchangers and associated piping and valves.

17. A new SGBS liquid condensate discharge radiation monitor.

B. pCE-to-NRC Correspondence and NRC-to-PGE Correspondence This correspondence includes analyses and information submitted to the NRC or prepared per NRC requirements and agreements made during NRC inspections. The following correspondence affects the FSAR and was incorporated in Amendment 10.

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!- Trajan Nuclcer Pltnt Docum:nt Control D:sk Docket 50-344 July 31, 1989 License NPF-1 Attachment Page 3 of 3 i

PGE.(D. W. Cockfield) to NRC (Document Control Desk) letter,

" Leak-Eefore-Break Analysis Final Report", dated March 14, 1988, transmitted for review Westinghouse Corporation's WCAP-11699 and

-11700. This submittal was approved by NRC (T. L. Chan) to PGE letter dated August 5, 1988. FSAR Sections 3.6, " Criteria for Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping", and 3.9, " Mechanical Systems and Components",

text and tables are revised to eliminate the dynamic effects of postulated large primary loop pipe ruptures from the structural design basis.

C. The following change resulted from internal PGE memoranda:

Section 13.1.2, " Nuclear Division", is revised to reflect a reorganization of the Nuclear Division with the addition of the new position General Manager, Plant Support reporting to the Vice President, Nuclear. Transferred from the General Manager, Trojan to Plant Support are: Manager, Administrative Services (formerly Plant Services); Manager, Planning and Control (formerly Outage Planning and Scheduling); and the Manager, Material Services. The position of Manager, Trojan Programs is deleted. Figures 13.1-1 and 13.1-2 are revised, and Figure 13.4-1 is deleted. The Manager, Training, will report to the General Manager, Plant Support, upon approval of LCA 182.

RLS/bsh 0107A.0789 I

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