ML20235J910

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Forwards Amend 6 to Updated Fsar.Amend Includes Effects of Changes Made in Facility or Procedures as Described in 820720 FSAR & Amends 1-5 & Safety Evaluation Performed by Util in Support of Requested License Amends
ML20235J910
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 07/01/1987
From: Cockfield D, Walt T
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235J913 List:
References
TDW-264-87, NUDOCS 8707160053
Download: ML20235J910 (37)
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Text

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a 2 muser David W. Cockfield Vice Pres; dent, Nuclear 1

July 1, 1987 Trojan Nucicar Plant Docket 50-344 {

License NPF-1 l l

U.S. Nuclear Regulatory Commission .

ATTN: Document Control Desk Washington DC 20555 l

Dear Sir:

Updated Final Safety Analysis Report. Amendment 6 A  ;

In accordance with Title 10, Code of Federal Regulations, Part 50.71(c),

{

) one original and 10 conformed copics of this letter and its attachments l I ,

are submitted in support of Amendment 6 to the Trojan Nuclear Plant Updated Final Safety Analysis Report (FSAR), 11 sets of which have boon transmitted under separate cover. This amendment includes the effects of: (a) changes made in the facility or procedures as described in the FSAR submitted on July 20, 1982 and reviced by Amendments 1 through 5; (b) safety evaluations performed by Fortland General Electric Company (PGE), either in support of requested licenso amendments or in support of conclusions that changes did not involvo an unroviewed safety question; and (c) analyses of new safety issues performed by or on behalf of PGE at the request of the Nuclear Regulatory Commission (NRC). 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 l Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, )

NUREC--0800 (July 1981). Each copy of Amendment 6 is accompanied by a set of instructions for inserting it into the FSAR. The replacement pages f

contain " change bars", ie, vertical lines in the margin adjacent to the portion actually changed, and each replacement page is labeled

" Amendment 6 (July 1987)".

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f3 8707160053 870701 l x

~) kDR ADOCK 05000344 """ \

l 121 SW Salmon Street. Pomand. Oregon 97204 L - - _ _ _ _ . _ _ _ _

r' - -- - - - -

Portland General ElectricCcAIMHif Document Control Desk O July 1, 1987 Page 2 The attachment identifies the changes due to analyses submitted to the NRC or prepared pursuant to NRC requirements and the changes made under Other provisions of Title 10, code of Federal Regulations, Part 50.59. -

major sources of amendment information are also identified.

Sincerely, bW ,

Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission

)

l Mr. R. C. Bare l NRC Resident Inspector Trojan Nuclear Plant l Mr. David Kish, Director State of Oregon O Department of Energy l Subscribed and sworn to before me this 1st day of July 1987.

/Le-6 s / / f* L Notary Public of Ore'gon

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Trojan Nuclear Plant Document Control Desk-July 1, 1987 Docket 50-344 License NPF-1 Attachment Page 1 of 7 V

UPDATED FINAL SAFETY ANALYSIS REPORT IDENTIFICATION OF AMENDMENT 6 CHANCES A. Plant Design Changes - Federal regulations (Title 1C, 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, ar.c tests or experiments to be conducted which are not described in the safety analysis report, without prior Nucicar Regulatory Commission (NRC) approval, unless the proposed change, test, or experiment involves a change in the Technical Specifications incorporated in the license or nn unreviewed safety question. The following Plant Desiga Changes were evaluated, and it was determined that they did not involve an unreviewed safety question.

1. Plant. Design Change 81-049 installed a Radioactive Solid Waste Processing Annex at the north end of the Fuel Building.

Sections 3.8.4.1.1.2 and 11.4.2 were revised and new Sections 3.8.4.1.13, 9.4.2.1.7 and 9.4.2.2.4 were added to reflect this change.

2. Plant Design Change 81-106 replaced the hydrogen vent valves O with qualified valves. Section 6.2.5.2 was revised to reflect that the valves are no longer required to be de-energized, l
3. Plant Design Change 85-001 modified certain Emergency Core Cooling System valves so they could be throttled. Section 6.3.2 l and Table 6.3-12 were revised to ref!.ect this change.

Plant Design Change 80-111 added the Reactor Vessel Level l 4.

Instrumentation System. A description of the system was incorporated in new Sections 7.6.1.8 and 7.6.2.8. Section 15.0 was als0 revised to reflect the change.

l S. Plant Design Change 78-065 added diesel air intake filter differential pressure gauges. Section 8.3.1.2.6 was revised to reflect this change.

6. Plant Design Change 82-022 added a turbine generator overcurrent l trip. Section 8.3.1.2.1 was revised to reflect this change. l J
7. Plant Design Change 84-128 changed the fuel transfer car from air drive to electric drive. Section 9.1.4.2.2.5 was revised to reflect this change. l
8. Plant Design Change 84-086 added fire protection cable wraps.

Sections 9.2.1.3 and 9.2.2.3 were revised to reflect this change.

Trojan Nuclear Plant Document Control Desk Docket 50-344 July 1, 1987 i Licence NPF-1 Attachment

\ Page 2 of 7

9. Plant Design Change 84-073 added the capability to recirculate the Condensate Storage Tank through the makeup water treatment system degasifier. Section 9.2 was revised to reflect this change.
10. Plant Design Change 82-080 added the capability to bubble nitrogen through the steam generators to mix chemicals in wet layup utilizing the nitrogen supply system. Section 9.3.5.1.3 was revised to reflect this change.
11. Plant Design Change 81-085 modified the electrical auxiliary room walls and ventilation to separate f.he Train A and Train B switchgear. Section 9.4.1 was revised to reflect this change.
12. Plant Design Change 80-081 expanded the capacity and capabilities of the Plant phone system. Section 9.5.2.2.1 was revised to reflect this change.
13. Plant Design Change 85-014 supplied the onsite equipment for the emergency notification system with an uninterruptible power supply. Section 9.5.2.2.3 was revised to reflect this change.

14 Plant Design Changes84-096 and 86-002 made reliability improvements to the Auxiliary Feedwater System. Section 10.4.9 and Table 10.4-18 were revised to reflect these changes. i

15. Plant Design Change 81-077 installed switches to block the auxiliary feedwater auto start on lov-low steam generator level and loss of main feedwater pump during maintenance.

Section 10.4.9.2.3.2 and Tables 10.4-18 and 10.4-20 were revised to reflect this change.

I

16. Plant Design Change 82-017 removed the process boiler making the packaged boiler the primary source of auxiliary steam for startup. Section 10.4 was revised to reflect this change.
17. Plant Design Change 85-030 replaced several feedwater heaters to change the feedwater heater tubes from copper to stainless steel. Table 10.4-9 was revised to reflect this change.
18. Plant Design Change 83-025 modified control room control of the turbine auxiliary feedwater pump steam valves for more reliable operation. Table 10.4-18 was revised to reflect this change.
19. Plant Configuration Change 85-549 installed an interlock to prevent waste gas compressor operation with water indicated in ,

the waste gas surge tank. Section 11.3.2.1 was revised to reflect this change.

t

r Trojan Nuclear Plant Document Control Desk Docket 50-344 July 1, 1987 n

License NPF-1 Attachment

{- Page 3 of 7 B. Licensing Document Change Requests (LDCRs) ~ Licensing documents consist of various Portland General Electric Company (PCE) Topical Reports and the Trojan Updated Final Safety Analysis Report (FSAR).

Under 10 CFR 50.59, changes are permitted to these documents if a

) 1 change to the Operating License or Technical Specifications does not result, and an unreviewed safety question is not created. The following LDCRs were evaluated, and it was determined that their ) !

changes do not involve a change to the Operating License, Technical Specifications, or an unreviewed safety or environmental question.

1. LDCR 86-15 described tho inservice testing program for pumps and i valves for the second 10-year interval in Topical Report PGE-1048. Section 3.9.6 was revised to reference the second 10-year program report.
2. LDCR 86-19 described the inservice inspection program for the '

second 10-year interval in Topical Report PGE-1049.

Sections 5.2.4 and 6.6 were revised to reference the second 10-year program report.

C. License Amendments - License amendments to the Trojan Operating License and Technical Specifications are approved by the NRC.

O Information from the follcwing license amendment is included in Amendment 6 to the FSAR.

I Operating License Amendment 48 changed the overpower AT setpoint to vary with coolant temperature. l Section 15.4.2.1 was revised to reflect this change. ,

D. PGE to NRC Correspondence and NRC to PGE Correspondence - This correspondence includes analyses and information submitted to the NRC or prepared por NRC requirements and agreements made during NRC inspections. The following correspondence affects the FSAR and was incorporated in Amendment 6,

1. PGE (B. D. Withers) to NRC (S. A. Varga) letter dated January 23, 1986 regarding pressurized thermal shock reference temperature. As a result of the pressurized thermal shock '

assessment, Section 5.3.1.5 was revised.

2. PGE (B. D. Withers) to NRC (H. L. Thompson) letter dated January 31, 1986 regarding automatic trip of reactor coolant pumps. As a result of this' letter, Section 5.4.1 was revised.
3. NRC (A. E. Chaffee) to PGE (W. J. Lindblad) letter dated April 21, 1987 discussed Type B leak rate testing of the fuel s

transfer tube bellows. As a result of this letter, Section 6.2.4.2.3 was revised.

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r Trojan Nucicar Plant Document Control Desk July 1, 1987

,-_ Docket 50-344 Licence NPF-1 Attachment

(\ Page 4 of 7

4. NRC (A. E. Chaffee) to PGE (W. J. Lindblad) letter dated' January 27, 1987 discussed changing the designation of Containment Penetration F-10 to a Type II penetration. As a result of this inspection report, Table 6.2-1 and Figure 6.2-7 were revised. ,
5. PCE (D. J. Broehl) to NRC (R. H. Engelken) letter dated September 24, 1980 regarding Inspection and Enforcement Bullet.in 80-18. As a result of this letter, the reactor coolant pump seal leakoff normal and backup paths were revised in Section 9.3.4.

E. Internal PGE memorandums, Nucione Steam Supply System vendor and Architect-Engineer correspondence, and correction of errors discovered in everyday use of the FSAR have resulted in revisions and editorial changes, including, but not limited to the following:

1. Tables and text describing equipment characteristics were revised throughout the FSAR to reficct drawing and vendor information.

g'"%g

2. Updated list of material incorporated by reference in  ;

g ,f Section 1.6.

3. Made the lists of Engineered Safety Features actuation devices which are not tested at power consistent throughout the FSAR.
4. Clarified the commitments for repair or replacement of .

t components in Section 3.2.2.

5. Added reference to the PGE Topical Report on environmental qualification (PCE-1025) to Sections 3.2.2 and 6.3.3.7.
6. Corrected the design tornado windspeed for the spent fuel pool in Table 3.3-2.
7. Added the service water strainer pit to Seismic Category 1 structures located below the design flood level in Section 3.4.
8. Corrected the Bechtel equation for safe shutdown earthquake total longitudinal stress in Section 3.7.3.3.3.4.
9. Clarified the design bases of the overpressure mitigation. system j in Sections 5.2.2 and 5.4.11. l
10. Revised the operating characteristics of the steam generator hydraulic shock suppressors to reflect new control valves in Section 5.4.12.1.7.

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7-l Trojan Nuclear Plant Document Control Desk {

Docket 50-344 July 1, 1987 (

License NPF-1 Attachment

\m/)

Page 5 of 7

11. Clarified Residual Heat Removal System flowpoths in Section 5.4.6.3.
12. Updated ste.am generator water chemistry limits in Tables 5.4-4 l and 10.4-10.  ;
13. Deleted discussion of failed Containment air cooler conditions in Section 6.2.2.3.5.
14. Updated the Containment isolation valve leak test methods in j Section 6.2.4.4. l
15. Updated the description of the recirculation mode in Section 6.3.3.
16. Changed reference to recirculation loop leakage in Section 6.3.3.
17. Design bases review of the Containment Spray System resulted in several changes in Section 6.5.2.  ;
18. Clarified bases for instrument accuracies in Sections 7.2.1.1, '

7.3.1.2 and 7.5.1. Revised accuracies in Tables 7.2-3, 7.3-4, O 19.

and 7.5-1.

Clarified Engineered Safety Features tests performed during j operation and shutdown in Section 7.3.

20. Revised Section 7.5 to reference PGE Topical Report on accident monitoring instrumentation (PGE-1043). ,
21. Revised Section 7.6.2.3 to reflect that the refueling interlocks are not safety-related in accordance with the Q-list.
22. Changed Section 7.7.1.10 to reference Section 8.3.1.4 for control board separation criteria.
23. Added description of possible transformer B10 overload if pressurizer heater groups are simultaneously energized from load center B10 to Section 8.3.1.1.4. ,

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24. Corrected emergency diesel generator insulation type in Section 8.3.1.1.6.
25. Incorporated updated 125 volt d-c battery requirements in Sections 8.3.2 and 9.4.1.1.2.
26. Revised Section 9.2.1.2.2.5 to indicato new methods of coating buried piping are being used.

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l Trojan Nuclear Plant Document Control Desk i Docket 50-344 July 1, 1987 License NPF-1 Attachment

' Pago 6 of 7 1

27. Updated method for throttling flow from the Circulating Water l System to the Service Water System in Section 9.2.1.2.3.6.
28. Incorporated revised equipment flooding analysis in Section 9.2.

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29. Clarified that only one Component Cooling Water System sarge tank safety valve is required to prevent system overpressuriza-tion in Section 9.2.2.2.2.3.

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30. Corrected Component Cooling Water System component designations, operating level and operating practices in Section 9.2.2.

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31. Revised Table 9,2-1 to reflect new Service Water System design l f

bases document.

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32. Corrected number of ch1;rine isolation valves and clarified l system operation in Sr: tion 9.3.6.2. I I
33. Clarified roll air filter efficiency in Section 9.4.
34. Added a description of ventilation system CB-14 to Section 9.4.1.
35. Corrected ventilation system CB-3 flow and ventilation system CB-5 filter designation in Section 9.4.1.2.3. i l
36. Clarified Section 9.4.1.3 to indicate the control room isolation f' dampers are Seismic Category I.
37. Revised high-efficiency particulate air filter efficiency to agree with the Technical Specifications in Section 9.4.2.
38. Corrected the auxiliary feedwater pamp diesel fuel oil day tank capacity in Section 9.5.4.2.

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39. Added references to the system figures in Section 9.5.9.2. )
40. Updated Turbine Building flood analysis in Section 10.4.6.3.
41. Corrected auxiliary feedwater pump head design criteria in ,

Section 10.4.9.1. I

42. Revised steam-driven auxiliary feedwater pump upper steam pressure in Section 10.4.9.1.
43. Revised Section 10.4.9.2.1 to include the turbine-driven auxiliary feedwater pump steam line guard pipe.

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1 Trojan Nuclear Plant Document Control Desk j Docket 50-344 July 1, 1987 l License NPF-1 Attachment 6

k Page 7 of 7

44. Clarified description of lines from condensate Storage Tank to auxiliary feedwater pumps in Section 10.4.9. {
45. Corrected valve MO-3170 power supply from d-c to a-c in Section 10.4.9.2.2.2. I
46. Updated the deceription of constant warming steam fic,w to the auxiliary feedwater steam turbine in Section 10.4.9.2.2.2.

I

47. Revised Section 10.4.9.2.2 to indicate the turbine auxiliary feedwater pump is self-cooled.
48. Revised Section 10.4.9 to indicate auxiliary feedwater pump discharge pressure is controlled using main steam line pressure.
49. Revised Section 10.4.9.3 to indicate auxiliary feedwater outlet valves are flow control valves. <

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50. Added the decontamination system to systems supplied with process steam in Section 10.4.10. l g 51. Indicated dirty waste drain tank volume in Section 11.2.2.1.2.1 v) l

- is usable volume.

52. Removed tritium analysis from Table 11.5-4.
53. Corrected description of radiation monitoring systems which are .

equipped with check sources in Section 11.5.2.

54. Referenced new shielding drawing in Section 12.3.2.  ;
55. Updated the number of Plant employees in Section 13.1.2.1.
56. Clarified equivalent Shift Technical Advisor training in Section 13.2.2.2.

I

57. Deleted Quality Ascurance Procedures from the types of Plant procedures in Section 13.5.
58. Added description of methods for accounting for feedwater flow element fouling to Section 15.0.5.
59. Corrected Section 15.1.2.2.1 to delete the statement that the feedwater pump discharge valves close automatically on a feedwater pump trip.
60. Added reference to the small break Loss-of-Coolant Accident
O NOTRUMP an lysis to Section 15.6.5.
61. Added results of thimble modeling and residual heat removal l miniflow failure analyses to Section 15.6.5.3.1.

SAB/FJ/kal/1431P.687

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emmres .

g Portland General ElectricCoirvisy July 1, 1987 I

I TDW-2 64 -87 ]

U. S. Nuclear Regulatory Commission l ATTN: Document Control Desk l Washington DC 20555 j I

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SUBJECT:

TROJAN NUCLEAR PLANT  !

Updated FSAR. Amendment 6 Enclosed is your copy of Amendment 6 to the Trojan Nuclear Plant Updated Final Safety Analysis Report. The pages are to be inserted in the subject document in accordance with the instruction sheet accompanying them.

Please acknowledge receipt by completing the lower portion of this l l

transmittal and returning it to the location shown below.

T. D. Walt, Manager Nuclear Safety & Regulation

. - - - . . . . .= ..._______

ACKNOWLEDGEMENT Trojan Nuclear Plant Updated Final Safety Analysis Report Amendment 6 42-54 I hereby acknowledge receipt of Controlled Copy Number (s) of the subject document. All changes have been made in accordance with the instructions and superseded pages have been destroyed or marked either "Vold" or " Superseded".

Signature of Copy Holder Date l

Return to: D. J. Harvey, SB Bridge Portland General Electric Company 121 S. W. Salmon Street Portland OR 97204 l

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'21 S W Salmon Street. Portland. Oregon 97204 I

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.. . . . . . ~ _ . . . . . __ . . , . , ,

m_____ _____2___

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( m ___ amma

' Pbrtland General ElectricCorpsy David W. Cockfield Vice President, Nuclear I

l July 1, 1987

}

Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission i ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Updated Final Safety Analysis Report. Amendment 6

-O In accordance with Title 10, Code of Federal Regulations, Part 50.71(c),

one original and 10 conformed copics of this letter and its attach:nents are submitted in support of Amendment 6 to the Trojan Nuclear Plant Updated Final Safety Analysis Report (FSAR), 11 sets of which have been transmitted under separate cover. This amendment includes the effects of: (a) changes made in the facility or procedures as described in the FSAR submitted on July 20, 1982 and revised by Amendments 1 through 5; (b) safety evaluations performed by Portland. General Electric Company l (PCE), either in support of requested license amendments or in support of l conclusions that changes did not involvo an unreviewed safety question; and (c) analyses of new safety issues performed by or on behalf of PGE at the request of the Nuclear Regulatory Commission (NRC). 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, NUREG-0800 (July 1981). Each copy of Amendment 6 is accompanied by a set of instructions for inserting it into the FSAR. The replacement pages cogitain " change bars", ie, vertical lines in the margin adjacent to the portion actually changed, and each replacement page is labeled

" Amendment 6 (July 1987)".

O 121 S.W Safrnon Sveet, Podland, Oregon 97204

< _ a

. l Portland Genem! BectricConway

/ Document Control Desk July 1, 1987 i i

Page 2  !

The attachment identifies the changes due to analyses submitted to the NRC or prepared pursuant to NEC requirements and the changes made under Other provisions of Title 10, Codo of Federal Regulations. Part 50.59. ,

major sources of amendment information are also identified. l Sincerely, Attachments c: Mr. John B. Martin i Regional Administrator, Region V f U.S. Nuclear Regulatory Commission Mr. R. C. Barr j NRC Resident Inspector j Trojan Nuclear Plant Mr. David Kish, Director (

State of Oregon Department of Energy Subt,cribed and sworn to before me this 1st day of July 1987.

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// p-fe_ fA f- 2V l Notary Public of Oregon

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  • My Commission Expires: e yew T N M s

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j Trojan Nuclear Plant Document Control Desk 3#17 1. 1987 O oeexet so-344 License NPF-1 Attachment Page l'of 7 UPDATED FINAL SAFETY ANALYSIS REPORT IDENTIFICATION OF AMENDMENT 6 CHANCES A. Plant Design 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 are not described in the safety analysis report, 1 J

without prior Nuclear Regulatory Commission (NRC) approval, unless '

the proposed chango, test, or experiment involves a change in the Technical Specifications incorporated in the license-or an unreviewed ,

l safety question. The following Plant' Design Changes were evaluated. }

and it was determined that they did not involve an unreviewed safety question.  ;

i

1. Plant Design Change 81-049 installed a Radioactive Solid Waste Processing Annex at the north end of the Fuel Building.

Sections 3.8.4.1.1.2 and 11.4.2 were revised and new Sections 3.8.4.1.13, 9.4.2.1.7 and 9.4.2.2.4 were added to reflect this change.

2. Plant Design Change 81-106 replaced the hydrogen vent valves with qualified valves. Section 6.2.5.2 was revised to reflect that the valves are no longer required to be de-energized.
3. Plant Design Change 85-001 modified certain Emergency Core Cooling System valves so they could be throttled. Section 6.3.2 and Table 6.3-12 were revised to reflect this chan68.
4. Plant Design Change 80-111 added the Reactor Vessel Level Instrumentation System. A description of the system was incorporated in new Sections 7.6.1.8 and 7.6.2.8. Section 15.0 f was also revised to reflect the change.
5. Plant Design Change 78-065 added diesel air intake filter differential pressure gauges. Section 8.3.1.2.6 was revised to reflect this change.
6. Plant Design Change 82-022 added a turbine generator overcurrent trip. Section 8.3.1.2.1 was revised to reflect this change.
7. Plant Design Change 84-128 changed the fuel transfer car from j

air drive to electric drive. Section 9.1.4.2.2.5 was revised to reflect this change.

8. Plant Design Change 84-086 added fire protection cable wraps.

Sections 9.2.1.3 and 9.2.2.3 were revised to reflect this change.

'l J

Trojan Nuclear Plant Document Control Desk f

() Docket 50-344 License NPF-1 July 1, 1987 Attachment l

Page 2 of 7

9. Plant Design Change 84-073 added the capability to recirculate j the Condensate Storage Tank through the makeup water treatment j j

system degasifier. Section 9.2 was revised to reflect this change. {

f Plant Design Change 82-080 added the capability to bubble I

10.  !

nitrogen through the steam generators to mix chemicals in wet layup utilizing the nitrogen supply system. Section 9.3.5.1.3 was revised to reflect this change.

11. Plant Design Change 81-085 modified the electrical auxiliary room walls and ventilation to separate the Train A and Train B switchgear. Section 9.4.1 was revised to reflect this change.

I

12. Plant Design Change 80-081 expanded the capacity and capabilities of the Plant phone system. Section 9.5.2.2.1 was revised to reflect this change.
13. Plant Design Change 85-014 supplied the onsite equipment for the emergency notification system with an uninterruptible power supply. Section 9.5.2.2.3 was revised to reficct this change.
14. Plant Design Changes84-096 and 86-002 nade reliability improvements to the Auxiliary Feedwater System. Section 10.4.9 and Table 10.4-18 were revised to reflect these changes.
15. Plant Design Change 81-077 installed switches to block the auxiliary feedwater auto start on low-low steam generator level and loss of main feedwater pump during maintenance.

l Section 10.4.9.2.3.2 and Tables 10.4-18 and 10.4-20 were revised to reflect this change.

16. Plant Design Change 82-017 removed the process boiler making the packaged boiler the primary source of auxiliary steam for startup. Section 10.4 was revised to reflect this change.
17. Plant Design Change 85-030 replaced several feedwater heaters to change the feedwater heater tubes from copper to stainless steel. Table 10.4-9 was revised to reflect this change.

l l 1P. Plant Design Change 83-025 modified control room control of the l

turbine auxiliary feedwater pump steam valves for more reliable l operation. Table 10.4-18 was revised to reflect this change.

19. Plant Configuration Change 85-549 installed an interlock to prevent waste gas compressor operation with water indicated in

() the waste gas surge tank. Section 11.3.2.1 was revised to reflect this change.

l

Trojan Nuclear Plant Document Control Desk

()'

Docket 50-344 License NPF-1 July 1, 1987 Attachment Page 3 of 7

(

j f

1 B. Licensing Document Change Requests (LDCRs) - Licensing documents l consist of various Portland General Electric Company (PGE) Topical )

j Reports and the Trojan Updated Final Safety Analysis Report (FSAR),

Under 10 CFR 50.59, changes are permitted to these documents if a  !

change to the Operating License or Technical Specifications does not f result, and an unreviewed safety question is not created. The following LDCRs were evaluated, and it was determined that their changes do not involve a change to the Operating License, Technical Specifications, or an unreviewed safety or environmental question.

1. LDCR 86-15 described the inservice testing program for pumps and valves for the second 10-year interval in Topical Report PGE-1048. Section 3.9.6 was revised to reference the second 1 10-year program report.
2. LDCR 86-19 described the inservice inspection program for the second 10-year interval in Topical Report PGE-1049.

Sections 5.2.4 and 6.6 were revised to reference the second 10-year program report. l C. License Amendments - License amendments to the Trojan Operating License and Technical Specifications are approved by the NRC.

(~)

'- Information from the following license amendment is included in Amendment 6 to the FSAR.

Operating License Amendment 48 changed the overpower AT setpoint to vary with coolant temperature. j Section 15.4.2.1 was revised to reflect this change.  !

D. PGE 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 6.

1. PGE (B. D. Withers) to NRC (S. A. Varga) letter dated January 23, 1986 regarding pressurized thermal shock reference temperature. As a result of the pressurized thermal shock assessment, Section 5.3.1.5 was revised.
2. PGE (B. D. Withers) to NRC (H. L. Thompson) letter dated January 31, 1986 regarding automatic trip of reactor coolant pumps. As a result of this letter, Section 5.4.1 was revised. ,

i

3. NRC (A. E. Chaffee) to PGE (W. J. Lindblad) letter dated April 21, 1987 discussed Type B leak rate testing of the fuel

(' transfer tube bellows. As a result of this letter, Section 6.2.4.2.3 was revised.

l i

Trojan Nuclear Plant Document Control Desk l July 1, 1987 f ')

(, Docket 50-344 Attachment License NPF-1 Page 4 of 7 )

4. NRC (A. E. Chaffee) to PGE (W. J. Lindblad) letter dated January 27, 1987 discussed changing the designation of Containment Penetration P-10 to a Type II penetration. As a result of this inspection report, Table 6.2-1 and Figure 6.2-7 were revised.
5. PGE (D. J. Brochl) to NRC (R. H. Engelken) letter dated September 24, 1980 regarding Inspection and Enforcement I Bulletin 80-18. As a result of this letter, the reactor coolant pump seal leakoff normal and backup paths were revised in Section 9.3.4.

E. Internal PCE memorandums, Nuclear Steam Supply System vendor and Architect-Engineer correspondence, and correction of errors l discovered in everyday use of the FSAR have resulted in revisions and editorial changes, including, but not limited to the following:

1

1. Tables and text describing equipment characteristics were l revised throughout the FSAR to reflect drawing and vendor information.

() 2. Updated list of material incorporated by reference in Section 1.6. '

1

3. Made the lists of Engineered Safety Features actuation devices  !

which are not tested at power consistent throughout the FSAR. l

4. Clarified the commitments for repair or replacement of components in Section 3.2.2.
5. Added reference to the PGE Topical Report on environmental qualification (PGE-1025) to Sections 3.2.2 and 6.3.3.7.
6. Corrected the design tornado windspeed for the spent fuel pool in Table 3.3-2.
7. Added the service water strainer pit to Seismic Category 1 structures located below the design flood level in Section 3.4.
8. Corrected the Bechtel equation for safe shutdown earthquake l total longitudinal stress in Section 3.7.3.3.3.4.
9. Clarified the design bases of the overpressure mitigation system in Sections 5.2.2 and 5.4.11.
10. Revised the operating characteristics of the steam generator i

() hydraulic shock suppressors to reflect new control valves in Section 5.4.12.1.7.

l

j i

1

' Trojan Nuclear Plant Document Control Desk- 1 Docket 50-344 ' July l', 1987 l License NPF-1= Attachment i Page 5 of 7 i l

11. Clarified Residual Heat Removal System flowpaths in Section 5.4.6.3.
12. Updated steam generator water chemistry limits in. Tables 5.4 f and 10.4-10,
13. Deleted discussion of failed Containment air cooler conditions l in Section 6.2.2.3.5.  :(

14 Updated the Containment isolation valve leak test methods in Section 6.2.4.4.  ;

15. Updated the description.of the recirculation mode in Section~ -
6. 3. 3. . y l
16. Changed reference to recirculation loop' leakage in Section 6.3.3.

17.. Design bases review of the Containment Spray System resulted in several changes in Section 6.5.2.

18. Clarified bases for instrument accuracies in Sections-7.2.1.1, 7.3.1.2 and 7.5.1. Revised accuracies in Tables 7.2-3, 7.3-4, .l and 7.5-1. ]

'I

19. Clarified Engineered Safety Features tests performed dur'is j operation and shutdown in Section 7.3.
20. Revised Section 7.5 to reference pGE Topical Report on eccident l monitoring instrumentation (PGE-1043).
21. Revised Section 7.6.2.3 to reflect that the refueling interlocks are not safety-related in accordance with the Q-list.
22. Changed Section 7.7.1.10 to reference Section 8.3.1.4 for  ;

control board separation criteria.

23. Added description of possible transformer B10 overload if pressurizer heater groups are simultaneously energized from load center B10 to Section 8.3.1.1.4.
24. Corrected emergency diesel generator insulation type in Section 8.3.1.1.6.
25. Incorporated updated 125 volt d-c battery requirements in.

Sections 8.3.2 and 9.4.1.1.2.

26. Revised Section 9.2.1.2.2.5 to indicate new methods of coating buried piping are being used.

i i

l J

Trojan Nuclear Plant Document Control Desk j Docket 50-344 July 1, 1987 l h* License NPF-1 Attachment Page 6 of 7

27. Updated method for throttling flow from the Circulating Water System to the Service Water System in Section 9.2.1.2.3.6.
28. Incorporated revised equipment flooding analysis in Section 9.2.

I

29. Clarified that only one Component Cooling Water System surge tank safety valve is required to provent system overpressuriza- (

tion in Section 9.2.2.2.2.3.

30. Corrected Component Cooling Water System component designations, operating level and operating practices in Section 9.2.2.
31. Revised Table 9.2-1 to reflect new Service Water System design bases document.

d

32. Corrected number of chlorine isolation valves and clarified l system operation in Section 9.3.6.2.

l

33. Clarified roll air filter efficiency in Section 9.4. )
34. Added a description of ventilation system CB-14 to Section 9.4.1. ]

E b 35. Corrected ventilation system CB-3 tiow and ventilation system l CB-5 filter designation in Section 9.4.1.2.3. {

36. Clarified Section 9.4.1.3 to indicate the control room isolation dampers are Seismic Category I. I
37. Revised high-efficiency particulate air filter efficiency to agree with the Technical Specifications in Section 9.4.2.
38. Corrected the auxiliary feedwater pump diesel fuel oil day tank )

capacity in Section 9.5.4.2. j j

39. Added references to the system figures in Section 9.5.9.2. j s

f

40. Updated Turbine Building flood analysis in Section 10.4.6.3.  !

)

41. Corrected auxiliary feedwater pump head design criteria in Section 10.4.9.1.  ;

I

42. Revised steam-driven auxiliary feedwater pump upper steam j pressure in Section 10.4.9.1.

1 I

43. Revised Section 10.4.9.7.1 to include the turbine-driven auxiliary feedwater pump steam line guard pipe. l n i V

1

Trojan Nuclear Plant Document Control Desk 3 17 1. 1987 i O oec*et so-344 License NPF-1 Attachment Page 7 of 7

44. Clarified description of lines from Condensate Storage Tank to auxiliary feedwater pumps in Section 10.4.9.
45. Corrected valve M0-3170 power supply from d-c to a-c in Section 10.4.9.2.2.2. {

i 1

46. Updated the description of constant warming steam flow to the auxiliary feedwater steam turbine in Section'10.4.9.2.2.2.
47. Revised Section 10.4.9.2.2 to indicate the turbine auxiliary feedwater pump ic self-cooled.  ;
48. Revised Section 10.4.9 to indicate auxiliary feedwater pump discharge pressure is controlled using main steam line pressure.
49. Revised Section 10.4.9.3 to indicate auxiliary feedwater outlet valves are flow control valves.

i

50. Added the decontamination system to systems supplied with process steam in Section 10.4.10. t Indicated dirty waste drain tank volume in Section 11.2.2.1.2.1 Q 51.

is usable volume, i

52. Removed tritium analysis from Table 11.5-4.

i Corrected description of radiation monitoring systems which are j 53.

equipped with check sources in'Section 11.5.2. l i

54. Referenced new shielding drawing in Section 12.3.2. l i
55. Updated the number of Plant employees in Section 13.1.2.1.
56. Clarified equivalent Shift Technical Advisor training in Section 13.2.2.2.
57. Deleted Quality Assurance Procedures from the types of Plant procedures in Section 13.5.
58. Added description of methods for accounting for feedwater flow element fouling to Section 15.0.5.
59. Corrected Section 15.1.2.2.1 to delete the statement that the feedwater pump discharge valves close automatically on a feedwater pump trip.
60. Added reference to the small break Loss-of-Coolant Accident O NOTRUMP analysis to Section 15.6.5.
61. Added results of thimble modeling and residual heat removal miniflow failure analyses to Section 15.6.5.3.1.

SAB/FJ/kal/1431P.687

l

& (PM ML" Portland GeneralElectricCompany David W. Cockfield Vice President, Nuclear July 1,.1987 i

Trojan Nuclear Plant Docket 50-344 License NPF-1 ,

1 i

U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk Washington DC 20555 1

Dear Sir:

Updated Final Safety Analysis Report. Amendment 6 s

In accordance with Title 10, Code of Federal Regulations, Part 50.71(e), q i

l one original and 10 conformed copics of this letter and its attachments l

are submitted in support of Amendment 6 to the Trojan Nuclear Plant Updated Final Safety Analysis Report (FSAR), 11 sett of which have boon 1

transmitted under separato cover. This amendment includes the effects of: (a) changes made in the facility or procedures as described in the  ;

FSAR submitted on July 20, 1982 and revised by Amendments 1 through 5; (b) safety evaluations performed by Portland General Electric Company (PCE), either in support of requested license amendments or in support of conclusions that changes did not involvo an unroviewed safety question; and (c) analyses of new safety issues performed by or on behalf of PGE at the request of the Nuclear Regulatory Commission (NRC). Administrative and editorial changes have been included, as well as technical j

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, NUREG-0800 (July 1981). Each copy of Amendment 6 is accompanied by a set of instructions for inserting it into the FSAR. The replacement pages  !

contain " change bars", ie, vertical lines in the margin adjacent to the i portion actually changed, and each replacement page is labeled

" Amendment 6 (July 1987)".

O 121 S W Satrnon Street. Port and. Oregon 97204

Pcxtiard k%zi'ivactric t Cortpcitly Document Control Desk

~ July 1, 1987 Page 2 The attachment identifies the changes due to analyses submitted to the NRC or prepared pursuant to NRC requirements and the changes made under Other provisions of Title 10, Code of Federal Regulations, Part 50.59.

major sources of amendment information are also identified.

Sincerely,

'l y ,,

Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission

]

Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant Mr. David Kish, Director State of Oregon O Department of Energy Subscribed and sworn to before me this 1st day of July 1987.

pt d!.?-b b L

. ,# , Notary Public of Oregon

/

My Commission Expires: e a T f /[c f

[ ]

@-~~I,* .

.4 O

l l

Trojan Nuclear Plant Document Control Desk I

July 1, 1987 Docket 50-344 Attachment f License NPF-1 Page 1 of 7 j 1

UPDATED FINAL SAFETY ANALYSIS REPORT f IDENTIFICATION OF AMENDMENT 6 CHANCES

)

A. Plant Design 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 are not described in the safety analysis report, without prior Nuclear Regulatory Commission (NRC) approval, unless the proposed change, test, or experiment involves a change in the Technical Specifications incorporated in the license or an unreviewed safety question. The following Plant Design Changes were evaluated, and it was determined that they did not involve'an unreviewed safety ,

l question.

1. Plant Design Change 81-049 installed a Radioactive Solid aste

' Processing Annex at the north end of the Fuel Building.

Sections 3.8.4.1.1.2 and 11.4.2 were revised and new l Sections 3.8.4.1.13, 9.4.2.1.7 and 9.4.2.2.4 were added to reflect this change.

2. Plant Design Change 81-106 replaced the hydrogen vent valves with qualified valves. Section 6.2.5.2 was revised to reflect that the valves are no longer required to be de-energized.
3. Plant Design Change 85-001 modified certain Emergency Core Cooling System valves so they could be throttled. Section 6.3.2 and Table 6.3-12 were revised to reflect this change. .
4. Plant Design Change 80-111 added the Reactor Vessel Level Instrumentation System. A description of the system was incorporated in new Sections 7.6.1'.8 and 7.6.2.8. Section 15.0 was also revised to reflect the change.
5. Plant Design Change 78-065 added diesel air intake filter differential pressure gauges. Section 8.3.1.2.6 was revised to reflect this change.
6. Plant Design Change 82-022 added a turbine generator overcurrent trip. Section 8.3.1.2.1 was revised to reflect this change.
7. Plant Design Change 84-128 changed the fuel transfer car from air drive to electric drive. Section 9.1.4.2.2.5 was revised to reflect this change.
8. Plant Design Change 84-086 added fire protection cable wraps.

Sections 9.2.1.3 and 9.2.2.3 were revised to reflect this change.

O

%/

i

\

i

  • 1 f

Trojan Nuclear Plant Document Control Desk

,s July 1, 1987

( ) Docket 50-344 License NPF-1 Attachment ,

Page 2 of 7 I

9. Plant Design Change 84-073 added the capability to recirculate the condensato Storage Tank through the makeup water treatment i j

system degasifier. Section 9.2 was revised to reflect this .

change.

10. Plant Design Change 82-080 added the capability to bubble i nitrogen through the steam generators to mix chemicals in wet j layup utilizing the nitrogen supply system. Section 9.3.5.1.3 l was revised to reflect this change.
11. Plant Design Change 81-085 modified the electrical auxiliary room walls and ventilation to separate the Train A and Train B j switchgcar. Section 9.4.1 was revised to reflect this change.
12. Plant Design Change 80-081 expanded the capacity and capabilities of the Plant phone system. Section 9.5.2.2.1 was I revised to reflect this change. i
13. Plant Design Change 85-014 supplied the onsite equipment for the emergency notification system with an uninterruptible power ,

supply. Section 9.5.2.2.3 was revised to reflect this change. l

()

14. Plant Design Changes84-096 and 86-002 made reliability ,

1 improvements to the Auxiliary Feodwater System. Section 10.4.9 l and Table 10.4-18 were revised to reflect these changes.

15. Plant Design Change 81-077 installed switches to block the auxiliary feedwater auto start on low-low steam generator level l and loss of main feedwater pump during maintenance.

Section 10.4.9.2.3.2 and Tables 10.4-18 and 10.4-20 were revised to reflect this change.

16. Plant Design Change 82-017 removed the process boiler making the packaged boiler the prime.ry source of auxiliary steam for startup. Section 10.4 was revised to reflect this change.
17. Plant Design Change 85-030 replaced several feedwater heaters to change the feedwater heater tubes from copper to stainless steel. Table 10.4-9 was revised to reflect this change.
18. Plant Design Change 83-025 modified control room control of the turbine auxiliary feedwater pump steam valves for more reliable operation. Table 10.4-18 was revised to reflect this change.
19. Plant Configuration Change 85-549 installed an interlock to prevent waste gas compressor operation with water indicated in I

the waste gas surge tank. Section 11.3.2.1 was revised to f"') reflect this change.

1 k

= l Trojan Nuclear Plant Document Control Desk Y Docket 50-344 July 1, 1987 License NPF-1 Attachment l Page 3 of 7 B. Licensing Document Change Requests (LDCRs) - Licer. sing documents. ,

consist of various Portland General Electric Company (PGE) Topical l Reports and the Trojan Updated Final Safety Analysis Report (FSAR). [

Under 10 CFR 50.59, changes are permitted to these documents if a l change to the Operating License or Technical Specifications does not i result, and an unreviewed safety question is not created. The 1 following LDCRs were evaluated, and it was determined that their_ ]

changes do not involve a change to the Operating License, Technical Specifications, or an unroviewed safety or environmental' question.

1. LDCR 86-15 described the inservice testing program for pumps and valves for the second 10-year interval in Topical Report PGE-1048. Section 3.9.6 was revised to reference the second 10-year program report.
2. LDCR 86-19 described the inservice inspection program for the l second 10-year interval in Topical Report PGE-1049. l I

Sections 5.2.4 and 6.6 were revised to reference the second 10-year program report.

C. License Amendments - License amendments to the Trojan Operating l License and Technical Specifications are approved by the.NRC.

Information from the following license amendment is included in i Amendment 6 to the FSAR. l Operating License Amendment 48 changed the overpower AT setpoint to vary with coolant temperature.

Section 15.4.2.1 was revised to reflect this change.

l D. PGE 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 l inspections. The following correspondence affects the FSAR and was incorporated in Amendment 6.

1. PGE (B. D. Withers) to NRC (S. A. Varga) letter dated January 23, 1986 regarding pressurized thermal shock reference temperature. As a result of the pressurized thermal shock assessment, Section 5.3.1.5 was revised.
2. PGE (B. D. Withers) to NRC (H. L. Thompson) letter dated January 31, 1986 regarding automatic trip of reactor coolant pumps. As a result of this letter, Section 5.4.1 was revised.
3. NRC (A. E. Chaffee) to PGE (W. J. Lindbind) letter dated April 21, 1987 discussed Type B leak rate testing of the fuel transfer tube bellows. As a result of this letter.

Section 6.2.4.2.3 was revised, l

l l

Trojan Nucicar Plant Document Control Desk

() Docket 50-344 License NPF-1 July 1, 1987 Attachment Page 4 of 7

4. NRC (A. E. Chaffee) to PGE (W. J. Lindblad) letter dated January 27, 1987 discussed changing the designation of Containment Penetration F-10 to a Type II penetration. As a result of this inspection report, Table 6.2-1 and Figure 6.2-7 were revised.
5. PGE (D. J. Brochl) to NRC (R. H. Engelken) letter dated September 24, 1980 regarding Inspection and Enforcement Bulletin 80-18. As a result of this letter, the reactor coolant pump seal leakoff normal and backup paths were revised in Section 9.3.4.

l l

l E. Internal PGE memorandums, Nucicar Steam Supply System vendor and Architect-Engineer correspondence, and correction of errors discovered in everyday use of the FSAR have resulted in revisions and editorial changes, including, but not limited to the following:

1. Tables and text describing equipment characteristics were revised throughout the FSAR to reflect drawing and vendor information.

() 2. Updated list of material incorporated by reference in Section 1.6.

3. Made the lists of Engineered Safety Features actuation devices which are not tested at power consistent throughout the FSAR.
4. Clarified the commitments for repair or replacement of components in Section 3.2.2.
5. Added reference to the PGE Topical Report on environmental l qualification (PCE-1025) to Sections 3.2.2 and 6.3.3.7.

! 6. Corrected the design tornado windspeed for the spent fuel pool in Table 3.3-2.

7. Added the service water strainer pit to Seismic Category 1 structures located below the design flood level in Section 3.4.

l 8. Corrected the Bechtel equation for safe shutdown earthquake total longitudinal stress in Section 3.7.3.3.3.4.

! 9. Clarified the design bases of the overpressure mitigation system in Sections 5.2.2 and 5.4.11.

l 10. Revised the operating characteristics of the steam generator

() hydraulic shock suppressors to reflect new control valves in Section 5.4.12.1.7.

Trojan Nuclear Plant Document Control Desk Docket 50-344 July 1, 1987 l(~\

License NPF-1 Attachment  !

Pate 5 of 7

11. Clarified Residual Heat Removal System flowpaths in Section 5.4.6.3.
12. Updated steam generator water chemistry limits in Tables 5.4-4 and 10.4-10.
13. Deleted discussion of failed Containment' air cooler conditions in Section 6.2.2.3.5.
14. Updated the Containment isolation valve leak test methods in Section 6.2.4.4.
15. Updated the description of the recirculation mode in Section j 6.3.3.

l

16. Changed reference to recirculation loop leakage in Section 6.3.3.
17. Design baces review of the Containment Spray System resulted in several changes in Section 6.5.2.
18. Clarified bases for instrument accuracies in Sections 7.2.1.1, l s 7.3.1.2 and 7.5.1. Revised accuracies in Tables 7.2-3, 7.3-4,

- and 7.5-1.

19. Clarified Engineered Safety Features tests performed during operation and shutdown in Section 7.3.
20. Revised Section 7.5 to reference PGE Topical Report on accident monitoring instrumentation (PGE-1043).
21. Revised Section 7.6.2.3 to reflect that the refueling interlocks are not safety-related in accordance with the Q-list.
22. Changed Section 7.7.1.10 to reference Section 8.3.1.4 for control board separation criteria.
23. Added description of possible transformer B10 overload if pressurizer heater groups are simultaneously energized from load center B10 to Section 8.3.1.1.4.
24. Corrected emergency diesel generator insulation type in Section 8.3.1.1.6.
25. Incorporated updated 125 volt d-c battery requirements in Sections 8.3.2 and 9.4.1.1.2.

i gy 26. Revised Section 9.2.1.2.2.5 to indicate new methods of coating i v buried piping are being used.

'l i

Trojan Nuclear plant Document Control Desk )

Docket 50-344 July 1, 1987 , .

' License NPF-1 Attachment i page 6 of 7 i

27. Updated method for throttling flow from the Circulating Water j System to the Service Water System in Section 9.2.1.2.3.6.

i

28. Incorporated revised equipment flooding analysis in Section 9.'2. l
29. Clarified that only one Component Cooling Water System surge  !

tank safety valve is required to. prevent system overpressuriza-tion in Section 9.2.2.2.2.3.

30. Corrected Component Cooling Water System component designations,  ;

operating level and operating practices in Section 9.2.2.

31. Revised Table 9.2-1 to reflect new Service Water System design-bases document.

i

32. Corrected number of chlorine isolation valvesLand clarified l system operation in Section 9.3.6.2.
33. Clarified roll air filter efficiency in Section 9.4.
34. Added a description of ventilation system CB-14 to Section 9.4.1. J O 35. Corrected ventilation system CB-3 flow'and ventilation system i CB-5 filter designation in Section 9.4.1.2.3. J l

1

36. Clarified Section 9.4.1.3 to indicate the control' room isolation dampers are Seismic Category I.
37. Revised high-efficiency particulate air filter efficiency to agree with the Technical Specifications in Section 9.4.2.
38. Corrected the auxiliary feedwater pump diesci fuel oil day tank capacity in Section 9.5.4.2.
39. Added references to the system figures in Section 9.5.9.2.
40. Updated Turbine Building flood analysis in Section 10.4.6.3.
41. Corrected auxiliary feedwater pump head design criteria in Section 10.4.9.1. ,

.i

42. Revised steam-driven auxiliary feedwater pump upper steam pressure in Section 10.4.9.1.
43. Revised Section 10.4.9.2.1 to include the turbine-driven :i auxiliary feedwater pump steam line guard pipe.

O i

L___ I

s Trojan Nuclear Plant Document Control Desk July 1, 1987 I\

Docket 50-344 Attachment License NPF-1 Page 7 of 7

44. Clarified description of lines'from condensate Storage Tank to l auxiliary foodwater pumps in Section 10.4.9.
45. Corrected valve MO-3170 power supply from d-c to a-c in Section 10.4.9.2.2.2.
46. Updated the description of constant warming steam flow to the auxiliary feedwater steam turbine in Section 10.4.9.2.2.2.
47. Revised Section 10.4.9.2.2 to indicate the turbine auxiliary feedwater pump is self-cooled.

48, Revised Section 10.4.9 to indicate auxiliary feodwater pump dischargo pressure is controlled using main steam line prer; cure.

49. Revised Section 10.4.9.3 to indicate auxiliary feedwater outlet valves are flow control valves.

~l

50. Added the decontamination system to systems supplied with process steam in Section 10.4.10.

! 51. Indicated dirty waste drain tank volume in Section 11.2.2.1.2.1 is usable volume.

52. Removed tritium analysis from Table 11.5-4.
53. Corrected description of radiation monitoring systems which are equipped with check sources in Section 11.5.2.
54. Referenced new shielding drawing in Section 12.3.2.
55. Updated the number of Plant employees in Section 13.1.2.1.
56. Clarified equivalent Shift Technical Advisor training in Section 13.2.2.2.
57. Deleted Quality Assurance Procedures from the types of Plant procedures in Section 13.5.
58. Added description of methods for accounting for feedwater flow element fouling to Section 15.0.5.
59. Corrected Section 15.1.2.2.1 to delete the statement that the feedwater pump discharge valves close automatically on a feedwater pump trip.

['l

\-

T 60. Added reference to the small break Loss-of-Coolant Accident NOTRUMP analysis to Section 15.6.5.

61. Added results of thimble modeling and residual heat' removal miniflow failure analyses to Section 15.6.5.3.1.

SAB/FJ/kal/1431P.687

i

( mumm, meme Portlanci General Electric Ccirpiniy . j David W. Cockfield Vice President, Nuclear July ~1, 1987

- Trojan Nuclear Plant

' Docket 50-344 License NPF-1 U.S. Nucicar Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Updated Final Safety Analysis Report. Amendment 6 O In accordance with Title 10 Code of Federal Regulations, Part 50.71(e),

one original and 10 conformed copics of this letter and its attachments are submitted in support of Amendment 6 to the Trojan Nuclear Plant Updated Final Safety Analysis Report (FSAR), 11 sets of which have boon transmitted under separate cover. This amendment includes the effects of: (a) changes made in the facility or procedures as described in the FSAR submitted on July 20, 1982 and revised by Amendments 1 through 5, l (b) safety evaluations performed by Portland Ceneral Electric Company (PGE), either in support of requested license amendments or in support of conclusions that changes did not involve an unroviewed safety question; and (c) analyses of new safety issues performed by or on behalf of PGE at the request of the Nuclear Regulatory Commission (NRC). 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 Plsn for the Review of Safety Analysis Reports for Nucicar Power Plants',

NUREC-0800 (July 1981). Each copy of Amendment 6 is accompanied by a set of instructions for inserting it into the FSAR. The replacement pages contain " change bars", ie, vertical lines in the margin adjacent to the portion actually changed, and cach replacement page is labeled

" Amendment 6 (July 1987)".

121 S W Sa!rnon Street Pon,and Oregon 97204

1 1

i PorUan:f Genera! Ele,d.ai Conpany 1 Document Control Deck

[]--

July 1, 1987 ]

l Page 2 j The attachment identifies the changes due to analyses submitted to the URC or prepared pursuant to NRC requirements and the changes made under Other provisions of ' Title 10, Code of Federal Regulations, Part 50.59.

major sources of amendment information are also identified.

Sincerely, b

/%W M l Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission .

1 Mr. R. C. Bare NRC Resident Inspector Trojan Nuclear Plant Mr. David Kish, Director State of Oregon l

Department of Energy l Subscribed and sworn to before me this n 1st day of July 1987.

. n

\

/f !. A ft*

_6 / ft du Notary Public of Oregon t  ?],

I

< da e T N /['

vI[./

7*l' My Commission Expires: *,

4 .- . ..

4 .

_n  ? - [j, tw 4

a). .v f

1 l

1

.i O '

l l

l 1

.)

Document Control' Desk a Trojan Nuclear Plant July 1, 1987 Docket 50-344 Attachment License NPF-1. Page 1 of 7 i

k UPDATED FINAL SAFETY ANALYSIS REPORT. i IDENTIFICATION OF AMENDMENT 6 CHANGES A. Plant' Design 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 are not described in the safety analysis report,'

without prior Nucicar Regulatory Commission (NRC) approval, unless the proposed change, test, or experiment involves n' change in'the-Technical Specifications incorporated in'the license or an unreviewed 'l safety question. The following Plant Design Changes.were evaluated, and it was determined that they did not involve an unreviewed safety-question.

1. Plant Design Change 81-049 installed a Radioactive Solid Waste Processing Annex at the north end of the Fuel Building.

Sections 3.8.4.1.1.2 and 11.4.2 were revised and new Sections 3.8.4.1.13, 9.4.2.1.7 and 9.4.2.2.4 were added to reflect this change.

Plant Design Change 81-106 replaced the hydrogen vent valves O 2.

with qualified valves. Section 6.2.5.2 was revised to reflect that the valves are no longer required to be de-energized.

3. Plant Design Change 85-001 modified certain Emergency Core Cooling System valves so they could be throttled. Section 6.3.2 and Table 6.3-12 were revised to reflect this change.
4. Plant Design Change 80-111 added the Reactor Vessel Level Instrumentation System. A description of the system was incorporated in new Sections 7.6.1.8 and 7.6.2.8. Section 15.0 was also revised to reflect the change.

d i

5. Plant Design Change 78-065 added diesel air intake filter differential pressure gauges. Section 8.3.1.2.6 was revised to ]

reflect this change.

6. Plant Design Change 82-022 added a turbine generator overcurrent trip. Section 8.3.1.2.1 was revised to reflect this change.
7. Plant' Design Change 84-128 changed the fuel transfer car from air drive to electric drive. Section 9.1.4.2.2.5 was revised to reflect this change.
8. Plant Design Change 84-086 added fire protection cable wraps.

Sections 9.2.1.3 and 9.2.2.3 were revised to reflect this change.

1

- _ _~

Trojan Nuclear Plant Document Control Desk Docket 50-344 July 1, 1987

(' Attachment

\

License NPF-1 Page 2 of 7

9. Plant Design Change 84-073 added the capability to recirculate the Condensato Storage Tank through the makeup water treatment system degasifier. Section 9.2 was revised to reflect this change.
10. Plant Design Change 82-080 added the capability to bubblo i nitrogen through the steam generators to mix chemicals in wet layup utilizing the nitrogen supply system. Section 9.3.5.1.3 was revised to reficct this chango.

I

11. Plant Design Change 81-085 modified the electrical auxiliary room walls and ventilation to separate the Train t and Train B switchgcar. Section 9.4.1 van revised to reflect this change.
12. Plant Design Change 80-081 expanded the capacity and capabilities of the Plant phone system. Section 9.5.2.2.1 was revised to reficct this change.
13. Plant Design Change 85-014 supplied the onsite equipment for the emergency notification system with an uninterruptible power supply. Section 9.5.2.2.3 was revised to reflect this change.

\/ 14. Plant Design Changes84-096 and 86-002 made reliability l improvements to the Auxiliary Foodwater System. Section 10.4.9 and Table 10.4-18 were revised to reflect these changes.

15. Plant Design Change 81-077 installed switches to block the auxiliary feedeater auto start on low-low steam generator level and loss of main feedwater pump during maintenance.  !

Section 10.4.9.2.3.2 and Tables 10.4-18 and 10.4-20 were revised to reflect this change.

16. Plant Design Change 82-017 removed the process boiler making the packaged coiler the primary source of auxiliary steam for startup. Section 10.4 was revised to reflect this change.
17. Plant Design Change 85-030 replaced several feedwater heaters to change the feedwater heater tubes from copper to stainless steel. Table 10.4-9 was revised to reflect this change. ,
18. Plant Design Change 83-025 modified control room control of the l turbine auxiliary feedwater pump steam valves for more reliable l operation. Table 10.4-18 was revised to reflect this chango.  ;
19. Plant Configuration Change 85-549 installed an interlock to prevent waste gas compressor operation with water indicated in

/~N the waste gas surge tank. Section 11.3.2.1 was revised to k-) reflect this change.

I a

Trojan Nuc1 car Plant Document Control Desk

()

, July.1, 1987

' Docket 50-344 License NPF-1 Attachment Page 3 of 7 B. . Licensing Document Change Roquests (LDCRs) - Licensing documents consist of various Portland Gonceal' Electric Company.(PGE) Topical Reports and the Trojan Updated Final Safety Analysis Report. (FSAR) .

Under 10 CFR 50.59, changes are permitted to these documents if a 1 chango to the Operating Licenso or Technical Specifications does not' result, and an unreviewed safety question is not created. The following LDCRs were evaluated, and it was determined that their .,

changes do not involve a change to the Operating License, Technical Specifications, or an unreviewed safety or environmental question.

1. LDCR 86-15 described the inservice testing program for pumps'and valves for the second 10-year interval ~in Topical Report.

PGE-1048. Section 3.9.6 was revised to reference the second 10-ycar program report.

l 2. LDCR 86-19 described the inservice in'pection s program for the second 10-year interval in Topical Report PGE-1049.

l Sections 5.2.4 and 6.6 were revised to reference the second.

10-year program report.

C. License Amendments - License amendments to the Trojan Operating l

() License and Technical Specifications are approved by the NRC.

Information from the following license amendment is included in l

Amendment 6 to the FSAR.

1 Operating License Amendment 48 changed'the overpower AT setpoint to vary with coolant temperature.

Section 15.4.2.1 was revised to reflect this change.

D. PCE to NRC Correspondence and NRC to PGE Correspondence - This I correspondence includes analyses and information submitted to the NRC 1 l

or prepared per NRC requirements and agreements made during NRC inspections. The following correspondence affects.the FSAR and was '

! incorporated in Amendment 6.

1. PGE (B. D. Withers) to NRC (S. A. Varga) letter dated January 23, 1986 regarding pressurized thermal shock reference temperature. As a result of the pressurized thermal shock assessment, Section 5.3.1.5 was revised.
2. PGE (B. D. Withers) to NRC (H. L. Thompson) letter dated January 31, 1986 regarding automatic trip of-reactor coolant pumps. As a result of this letter, Section 5.4.1 was revised.
3. NRC (A. E. Chaffeo) to PGE (W. J. Lindblad). letter dated April 21, 1987 discussed Type B leak rate testing of the. fuel transfer tube bellows. As a result of this letter,

() Section 6.2.4.2.3 was revised.

Trojan Nuclear Plant Document Control' Desk July 1.-1987 Docket 50-344-License NPF-1 Attachment Page 4 of 7

4. NRC (A. E. Chaffeo) to PGE (W. J. Lindblad) letter dated-January 27, 1987 discursed changing the designation of

' Containment Penetration P-10 to a Type II penetration. As-a result of this inspection report, Table 6.2-1 and Figure 6.2-7 were revised.

i

5. PGE (D. J. Broch1) to NRC (R. H. Engelken) letter dated September 24, 1980 regarding Inspection and Enforcement j Bulletin 80-18. As a result of this. letter, the reactor coolant pump seal leakoff normal and backup paths were revised in ]

j Section 9.3.4.

E. Internal.PGE memorandums, Nuclear Steam Supply System vendor and Architect-Engineer correspondence, and correction of errors .

i discovered in everyday use of the FSAR have resulted in revisions and I editorial changes, including, but not limited to the following:
1. Tables and text describing equipment characteristics were .

1 revised throughout the FSAR to reflect drawing and vendor j

information.  !

2. Updated list of material incorporated by reference in )

Section 1.6.

Made the lists of Engineered Safety Features actuation devices i 3.

which are not tested at power consistent throughout the FSAR.

4. Clarified the commitments for repair or replacement of components in Section 3.2.2.
5. Added reference to the PGE Topical Report on environmental qualification (PGE-1025) to Sections 3.2.2 and 6.3.3.7.
6. Corrected the design tornado windspeed for the spent fuel pool i in Table 3.3-2.
7. Added the service water strainer pit to Seismic Category 1  ;

structures located below the design flood level in Section 3.4.

8. Corrected the Bechtel equation for safe shutdown earthquake total longitudinal stress in Section 3.7.3.3.3.4.
9. Clarified the design bases of the overpressure-mitigation system ,

in Sections 5.2.2 and 5.4.11.  !

10. Revised the operating characteristics of the steam generator hydraulic shock suppressors to reflect new control valves in l

j Section 5.4.12.1.7.

l

.-- ._. - _ _ _ _ . .___-__2____________ _

Trojcn Nuclear Plant Document Control Desk

() Docket 50-344 License NPF-1 July 1, 1987 Attachment Page 5 of 7 i

11. Clarified Residual Heat Removal System flowpaths in Section 5.4.6.3.
12. Updated steam generator water ehemistry limits in Tables 5.4-4 and 10.4-10.
13. Deleted discussion of failed Containment air cooler conditions in Section 6.2.2.3.5.

1

14. Updated the Containment isolation valve leak test methods in Section 6.2.4.4.
15. Updated the description of the recirculation mode in Section 6.3.3.
16. Changed reference to recirculation loop leakage in Section 6.3.3.
17. Design bases review of the Containment Spray System resulted in several changes in Section 6.5.2.
18. Cicrified bases for instrument accuracies in Sections 7.2.1.1, 7.3.1.2 and 7.5.1. Revised accuracies in Tables 7.2-3, 7.3-4, f]

V and 7.5-1.

19. Clatified Engineered Safety Features tests performed during operation and shutdown in Section 7.3.
20. Revised Section 7.5 to reference PGE Topical Report on accident monitoring instrumentation (pGE-1043).
21. Revised Section 7.6.2.3 to reflect that the refueling interlocks are not safety-related in accordance with the Q-list.
22. Changed Secticn 7.7.1.10 to reference Section 8.3.1.4 for control board separation criteria.
23. Added description of possible transformer B10 overload if pressurizer heater groups are simultaneously energized from load center B10 to Section 8.3.1.1.4.
24. Corrected emergency diesel generator insulation type in Section 8.3.1.1.6.
25. Incorporated updated 125 volt d-c battery requirements in Sections 8.3.2 and 9.4.1.1.2.

) 26. Revised Section 9.2.1.2.2.5 to indicate f.ew methods of coating

(/

\- buried piping are being used.

r- -------------------------o l

Trojan Nucicar Plant Document Control Dock l

/~h Docket'50-344 July 1, 1987

-l- License NPF-1 Attachment ,

Page 6 of 7 l

27. Updated method for throttling flow from the Circulating Water System to the Service Water System in Section 9.2.1.2.3.6.
28. Incorporated revised equipment flooding analysis in Section 9.2.
29. Clarified that only one Component Cooling Water System surge tank safety valve is required to prevent system overpressuriza-tion in Section 9.2.2.2.2.3.
30. Corrected Component Cooling Water System component designations, operating icvel and operating practices in Section 9.2.2.

i

31. Revised Table 9.2-1 to reflect new Service Water System design bases document. ]
32. Corrected number of chlorine isolation valves and clarified system operation in Section 9.3.6.2.
33. Clarified roll air filter efficiency in Section 9.4.
34. Added a description of ventilation system CD+14 to Section 9.4.1.

(/

i

35. Corrected ventilation system CB-3 flow and ventilation system j CB-5 filter designation in Section 9.4.1.2.3. l
36. Clarified Section 9.4.1.3 to indicate the control room isolation i dampers are Seismic Category I.  !
37. Revised high-officiency particulate air filter efficiency to agree with the Technical Specifications in Section 9.4.2.
38. Corrected the auxiliary feedwater pump diesel fuel oil day tank q capacity in Section 9.5.4.2.
39. Added references to the system figures in Section 9.5.9.2.
40. Updated Turbine Building flood analysis in Section 10.4.6.3.
41. Corrected auxiliary feedwater pump head design criteria in Section 10.4.9.1.
42. Revised steam-driven auxiliary feedwater pump upper steam pressure in Section 10.4.9.1.
43. Revised Section 10.4.9.2.1 to include the turbine-driven auxiliary feedwater pump steam line guard pipe.

O(../ 3 i

i i

r- ,

4

-e Trojan Nucicar Plant Document Control Desk Docket 50-344 July 1, 1987 License NPF-1 Attachment s Page 7 of 7

44. Clarified description of lines from Condensato Storage Tank to auxiliary feedwater pumps in Section 10.4.9.  !
45. Corrected valve MO-3170 power supply from d-c to a-c in Section 10.4.9.2.2.2.

l

46. Updated the description-of constant warming' steam flow to the auxiliary feedwater steam turbine in Section 10.4.9.2.2.2. 1
47. Revised Section 10.4.9.2.2 to indicato the turbine auxiliary-  !

feedwater pump is self-cooled.

48. Revised Section 10.4.9 to indicato auxiliary feodwater pump discharge pressure is controlled using main steam line pressure.
49. Revised Section 10.4.9.3 to indicate auxiliary feedwater outlet valves are flow control valves.
50. Added the decontamination system to systems supplied with process steam in Section 10.4.10,
51. Indicated dirty waste drain tank volume in Section 11.2.2.1.2.1 .

'- is usable volume.

52. Removed tritium analysis from Table 11.5-4. l
53. Corrected description of radiation monitoring systems which are equipped with check sources in Section 11.5.2.
54. Referenced new shielding drawing in Section 12.3.2.
55. Updated the number of Plant employees in Section 13.1.2.1.
56. Clarified equivalent Shift Technical Advisor training in Section 13.2.2.2.
57. Deleted Quality Assurance Procedures from the typec of Plant procedures in Section 13.5.
58. Added description of methods for accounting for feedwater flow element fouling to Section 15.0.5.
59. Corrected Section 15.1.2.2.1 to delete the statement that the feedwater pump discharge valves close automatically on la feedwater pump trip.
60. Added reference to the small break Loss-of-Coolant Act:ident

(]

v NOTRUMP analysis to Section 15.6.5.

61. Added results of thimble modeling and residual heat removal miniflow failure analyses to Section 15.6.5.3.1.

SAB/FJ/kal/1431P.687

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