ML20203J382

Annual Rept of Trojan Nuclear Plant for 1997

ML20203J382
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1997
From:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PGE-1015-97, VPN-011-98, VPN-11-98, NUDOCS 9803040077
Download: ML20203J382 (32)

Text

_ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

f c, h Portland Genernt Electric One Wrld Trade Center 12! SW Salmon Street Portland. OR 97204 Februar,126,1998 VPN-Oll-98 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission E ATTN: Document Control Desk Washington, DC 20555 PGE-1015-97. " Annual Renort of the Troian Nuclear Plant" The enclosure to this letter provides one copy of Portland General Electric Company's " Annual Report of the Trojan Nuclear Plant" for the calendar year 1997. This report is submitted in accordance with the requirements of 10 Code of Federal Regulations 50.59(b)(2) and Trojan Technical Specification 5.8.1.

Sincerely,

&w -

Stephen M. Quennoz Trojan Site Executive Enclosure c: D. Stewart-Smith, OOE ,7 i

R. A. Scarano, NRC Region IV /j;p l i L. Thonus, NRC, NRR '

s I

~

9803040077 971231 DR ADOCK 050003 4 ll- l< l, ll>llll .l Natural gas. Electricity. Endless possibilities.

. }

'a Trojan Nuclear Plant ANNUAL REPORT OF TROJAN NUCLEAR PLANT FOR 1997 PORTLAND GENERAL ELECTRIC COMPANY PGE-1015-97 1

PGE 1015-97 1997 AhWUAL REPORT for TROJAN NUCLEAR PLANT Docket 50-344 License NPF-1 PORTLAND GENERAL ELECTRIC COMPANY 121 S. W. Salmon Street Portland, Oregon 97204 l

TABLE OF COh' TENTS P;iss INTRODUCTION &

SUMMARY

OF OPERATING EXPERIENCE . . . . . . . . . . . . . . . . . , , ii 1, Annual Personnel Exposure and Monitoring Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

2. Changes, Tests, and Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 l

i

.._ a

(

(:-

INTRODUCTION The 1997 Annual Report for Trojan Nuclear Plant is submitted in accordance with the requirements of Possession Only License NPF 1, Appendix A,; ennanently Defueled Technical Specificadon 5.8.1 and 10 CFR 50.59(b)(2).

SUMMARY

OF OPERATING EXPERIENCE IN 1997

[

Throughout the entire year, the plant remained permanently shutdown with the fuel removed from the reactor vessel.

[

l

{

l

{

(<

{

[ ii

(

l

1. ANNU AL PERSONNEL EXPOSURE AND MONITORING REPORT Requirement

. Trojan Possession Only License NPF 1, Appendix A Permanently Defueled Technical Specification 5.8.1.1, requires that an annual report be submitted which includes:

" Occupational Radiation Exposure Report shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures

> 100 mrem /yr and their associated man rem exposure according to work and job functior :: g., fuel handling, surveillance, maintenance and waste processing). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totaling < 20% of the individual total dose need not be accounted for, in the aggregate, at least 80%

of the total whole body dose received from external sources should be assigned to specific major work functions." 4 Recrt Table 1 lists the number of v.orkers receiving total exposures greater than 100 mrem per year and the total exposures by work and job function for the year 1997 based on self-reading dosimeter results. The " Total" and " Grand Total" sections of the table are based on self-reading dosimeters.

All work performed for dismantlement and decommissioning was classified as work function "Special Maintenance" and spent fuel pool debris removal work was classified as " Waste Processing." All of the contractors for dismantlement and decommissioning activities were classified as job function " Maintenance" and for debris removal as job function " Operations." Note that contracted personnel represented 56% of exposed workers and 69% of 1997 reported dose.

I

TAHll 1 l Sheet I of 2 l

REPORT ON NUMBER OF PERSONNEL AND MAN-REM DY WORK AND JOB FUNCTIONS 1997 No. of Personnel (>100 traemi Total Man Rem f >100 mrem)

Station Utility Contract Station Utility Contract Work and Job Function Emnlovees Emnlovees Worke.s Emnlovees Emnlovers Workers REACTOR OPERATIONS & SURVEILLANCE Maintenance Personnel 0 0 1 0.00 0.00 0.162 Operating Personnel 0 0 0 0.00 0.00 0.00 llealth Physics Personnel 0 0 0 0.00 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 Engineering Personnel 3 1 0 0.00 0.143 0.00 ROUTINE MAINTENANCE Maintei.ance Personnel 0 0 0 0.00 0.00 0.00 Operating Personnel 0 0 0 0.00 0.00 0.00 llealth Physics Personnel 0 0 0 0.00 0.00 0.00 Supervisory Pemonnel 0 0 0 0.00 0.00 0.00 Engineering Pe.sonnel 0 0 0 0.00 0.00 0.00 INSERVICE INSPECTIONS Maintenance Personnel 0 0 0 0.00 0.00 0.00 Operating Personnel 0 0 0 0.00 0.00 0.00 licalth Physics Personnel 0 0 0 0.00 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 Engineering Personnel 0 0 0 0.00 0.00 0.00 SPECIAL MAINTENANCE Maintenance Personnel 13 11 63 2.407 3.221 25.442 Operatug Personnel 1 0 0 0.175 0.00 0.00 llealt.. Physics Personnel 19 0 0 3.694 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 Engineering Personnel 1 0 0 0.204 0.00 0.00 2

s -

TABLEI Sheet 2 of 2 REPORT ON NUMBER OF PERSONNEL AND MAN REM BY WORK AND JOB FUNCTIONS 1997 No. of Personnel (>100 mremi TotalMan Rem (>100 mrem)

Station Utility Contract Station Utility Contract Work and Job Function Emnloyees Emnlovees Werlers Emnlovees Emnloveqs ,WpAgn WASTE PROCESSING McIntenance Personnel 4 1 3 0.773 0.101 0.473 Operating Personnel 1 0 7 0.169 0.00 1.105 llealth Physics Personnel 6 0 0 1.181 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 Engineering Personnel 0 0 0 0.00 0.00 0.00 REFUELING j Maintenance Personnel 0 0 0 0.00 0.00 0.00 Operating Personnel 0 0 0 0.00 0.00 0.00 llealth Physics Person el 0 9 0 0.00 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 j Engineering Personnel 0 0 0 0.00 0,00 0.00 I

I l

TOTAL Maintenance Personnel 17 12 67 3.180 3.323 26.077 Operating Personnel 2 0 7 0.344 0.00 1.105 llcalth Physics Personnel 25 0 0 4.875 0.00 0.00 Supervisory Personnel 0 0 0 0.00 0.00 0.00 Engineering Personnel 1 1 0 0.204 0.143 0.00 GRAND TOTAL 45 13 74 8.603 3.466 27.182 3

o

2. CIANGES.TINIL AND EXpl311MENTS Ikuitement Federal Regulation 10 CFR 50.59 requires:

"(a)(1) The holder of a license authorizing operation of a production or utilization facility may (i) make changes in the facility as described in the safety analysis report,(ii) make changes in the proceduren as described in the safety analysis report, and (iii) conduct tesu or experiments not describc<1 in the safety analysis report, without prior Commission approval, unless the proposed change, test or experiment involves a changr in the technical specifications l incorporated in the license or an unreviewed safety question.

(b)(2) The licensee shall submit as specified in s 50.4, a report I containim; a brief desciiption of any changes, tests, and experiments,incluthng a summary of the safety evaluation of each...annuat' " ..

IkD2Il Section 2 of the Annual Report provides a description of changes, tests, and experiments completed in 1997 in accordance with 10 CFR 50.59 and a summary of the supporting safety evaluation.

4

199710 CFR 50.59 Annual Heport hfety Evaluating Numbtt 96 007 Suldtti Amendment 14 to Poli 1021. "Offsite Dose Calculation hianual (ODCht)," to implement Sub Part D of10 CFR 20 Dnctlp11on.0LChangc. Test Entriment The ODChi was revised to implement Subpart D cf 10 CFR 20 and Appendix il of 10 CFR 20.1001 to 20.2402 for gaseous and liquid effluent releases. Changes were made for controlling, monitoring, and reporting rad:ologbal emuents and environmental impacts. The changes maintain the same overall level of efhnt control while retaining the operational flexibility that existed with fonner nDChi provisions. The ODChi continues to require that radiation doses to members of the public from gaseous and liquid emuent releases from nuclear power plants be within the values given in Appendix 1 to 10 CFR 50. Text changes reflect corrected or update information resulting from decommissioning activities as well as editorial changes.

S.ummary of SaftlLEratuation The changes were detemiined to maintain the levels of radioactive emuent control required by 10 CFR 20.1302 and 40 CFR 190, and do not adversely impact the accuracy or reliability of emuent, dose, or setpoint calculations. The changes were also detemiined to maintain the overall conformance of the solidified waste product to the existing requirements of Federal, State, or other applicable regulations. The changes to the ODChi do not increase the probability of occurrence of, or consequences from, an accident previously evaluatea in the Defueled Safety Analysis Report (DSAR). These changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes are not associated with plant equipment design, operation, or maintenance and will not result in any degradation i'i the reliability of structures, systems, or con ponents. The changes do not involve a reduction in the number and type of environmental samples analyzed or alter the verification of the accuracy of the emuent monitoring program and modeling of exposure pathways.

These changes do not affect the margin of safety as delined in the Trojan Technical Specifications or Bases. Therefore, these changes do not involve an unreviewed safety c,uestion because,(1) there is no increase in the probability of occurrence or the consequences of an eccident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

5

199710 CFR 50.59 Annual Report SAicly_lhBluglinn Number 96-032 Subjett Defueled Plant hiodincation Request (DPhiR)96-001, Detailed Corstruction Package (DCP) 3, "93 Foot Fuel Iluilding Independent Spent Fuel Storage Installation (ISFSI) L.oad Path Structural hiodi0 cations" Ilcicrhttlun of Change. Test. Experiment This DPhiR modined walls and structures '.o accommodate the ISFSI cask travel path. Portions of the ceiling and walls of the radioactive tool storage area (Room 284) were removed, as well as a stub wall and Door 193 into the former hot tool room.

SuntinaQ3f_Silfsty Evalitalian These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. hiodincation to the boric acid piping does not increase the probability of, or consequences from, a fuel handling acsident. lloric acid is a mitigating factor after an accident has occurred. The modi 0 cation does not alter the amount of boron available in the water or prevent addition of added boron by other means. Rubber hose used to replace riping is reted for a pressure in excess of the supply pressure. These changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes are not associated with plant equipment design, operation, or maintenance and will not result in any degradation in the reliability of structures, systems, or components.

These changes do not affect the margin of safety as denned in the Trojan Technical Speci0 cations or Bases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR, (2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as denneo m the basis for any technical speci0 cations is not reduced.

6

199710 CH150.59 Annual Report Saft1LJhsluallanhumher 96 034 Satldtti DPMR 96 013, DCP 1,"'A' Train Service Water llooster Pump Removal" 11ticrin11on_nLChangcJEntJhprdment This DCP removed two A Train Service Water llooster Pumps (SWilPs) and the SWilP area cooler. These components were removed to provide an area for temporary staging of deactivated material / equipment. Associated interferences (e.g., hanger, supports, and Orc protection equip.)

were also removed. The Service Water System was re classined to Seismic Category (SC)11.

The Defueled Safety Analysis Report (DSAR) and PGD1061," Trojan Nuclear Plant Decommissioning Plan," were revised to reference two SWilPs and two loops of Service Water System makeup to the spent fuel pool.

l SuminatLOL%ift1LErahtallun i These changes do not increase the probability ofoccurrence of, or consequences from, an accident previously evaluated in the DS AR. No new failure modes that could lead to a loss of spent fuel pool inventory are created. The changes are bounded by the evaluated accidents in the DSAR. No credit is taken in any evaluated accidents described in the DSAR for a Service Water System SC 1 makeup path or for redundant Service Water System makeup paths to the spent fuel pool. These :hanges will not result in any degr Jation in the reliability of structures, systems, or components credited in the DSAR. The DCP and reclassincation of tla Service Water System do not reduce the number of available spent fuel pool makeup water sources as listed in the DSAR and Design 11 asis Document. The remaining SWilPs provide makeup to the spent fuel pool in excess of the required Dowrate. These changes do not affect the margin of safety as denned in the Trojan Technical Speci0 cations (TS) or flases. The changes do not require or allow reductions in minimum spent fuel pool water level or boron concentration below that specified in the TS; nor do they require or allow increases in maximum spent fuel pool temperature and/or impact energies.

Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accideni or malfunction of equipment important to safety previously evaluated in the DSAR, (2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as denned in the basis for any technical specincations is not reduced.

7

199710 Cl it 50.59 Annual iteport SAILlyfralunflon Numiltt 96 045 l

Sulljtti l Maintenance Requests (MRs) 10625,10626,10627, and 10628 DutrJ ittun of ChangcJntluttrintent These MRs removed miscellaneous interferences on various Auxiliary and Fuel lluilding elevations and the residual heat removal heat exchanger access floor plugs. The affected equipment was previously deactivated. The radiation shielding formerly supplied by the floor plugs is no longer necessary.

Suinnlan of Snftt>llaluation These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. None of the affected components are required to support the safe storage ofirradiated fuel. 'these changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes are not associated with plant equipment design, operation, or maintenance and will not result in any degradation in the reliability of structures, systems, or components.

These changes do not affect the margin of safety as denned in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an ,

accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

f

(

8

199710 CI'R 50.59 Annual 1(cport Saftty Esatuanon Number 96 058 Subjtst Decommissioning Work Plan (DWp) D0002," Decommission the ' A' Residual llent Removal (RilR) Pump and llcat Exchanger Rooms" ncKrlWinn of Chungc. Test. Experlmtnt DWP 00002 disconnected and rernoved equipment from the 'A' RilR heat exchanger and pump rooms on the Auxiliary llullding five foot elevation (Rooms 125 and O including isolating instrument air supply and eliminating a smoke detectot in the room. ca..dM changes to licensing documents were incorporated by Licensing Document Chat.p sps t (LDCR)

]

96 021.

SuminarLnflaftty Eiatuallon These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. No equipment important to safety was affected by the removal activities. The changes do not impact any system or components required to suPfort the safe storage of spent fuel. These changes do not afTect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR. The changes do not increase the combustible loading in the area of the spent fuel pool nor do they change the inherent Ere resistance in the design of the spent fuel pool.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

9

199710 CFR 50.59 Annual Report Saftty Evaluallunliumhtr 96 061 Subject DPMR 96-001, DCP 6," Removal / Relocation of Components to Support Removal of Portions of

( the Walls and Floor of the Decontamination Shop and Radioactive Waste Storage Area" lltitrinflun 0LQiangt. Test. Emptrimtal

( This DCP supports the removal / relocation of electrical and mechanical equipment attached to the 93 foot walls and Doors of the Fuel lluilding Decontamination Room and Radioactive Waste r Storage Area. Table 3.31 to POE 1012," Trojan Nuclear Plant Fire Protection Plan," was L revised to delete a sprinkler system in the radioactive waste storage area.

( SumnintrolSafttrEraluation L

These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The modi 0 cations do not impact equipment related to the spent fuel pool cooling or make up now paths, and no loads were moved over the area of

{ the spent fuel pool. These changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes are not associated with

( plant equipment design, operation, or maintenance and will not result in any degradation in the reliability of structures, systems, or components. No structural modincations to the building were made as part of this DCP.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question

( because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR, (2) a rassibility for an accident or malfunction of a different type than any evaluated previously in

[ the DSAR is not created, and (3) the margin of safety as denned in the basis for any technical specifications is not reduced.

[

[

[

{

[ 10

[

199710 CFR 50.59 Annual Report Safety Evaluatjon Numbtr 97 001 Subjtti DPMR 96 026, DCP 1," Residual lleat Removal (RilR) Decommissioning Interference Removal / Relocation" Dutription of ChungcJSil&ptriment This modification installed positive isolation between the spent fuel pool and the RilR Systems, including the connection to the refueling cavity. These closures eliminate the connection on the suction and discharge portion of the piping. This modification was performed to support decommissioning and dismantlement activities in locations where this piping is located. DSAR, Figure 3.3 1, was revised to show the modifications to the connections.

Suntmary of Safety Evalunilan These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. These changes do not adversely affect any plant equipment or the processes and procedures for responding to an equipment raalfunction. These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR. The installation of positive isolations eliminated problems due to inadvcitent opening of critical valves. This modification does not affect the ability to maintain the temperature of the pool within acceptable limits, nor does it affect the ability to maintain water level over the required depth. Installation of the blanks and caps provide a higher degree of confidence that the water level in the pool can be maintained. The installation of blanks and caps and the removal of portions of the piping from the refueling cavity do not degrade the capability to maintain boron concentration in the pool. Modifications in this package comply with Administrative controls outlined in Section 5.0 of the Technical Specifications.

These changes do not effect the margin of safety as defined in the Trojan Technical Specifications or flases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

11

199710 CFit 50.59 Annual Report Safety Evaluation Number 97 002 S11bjtti Trojan Plant Procedure (TPP) 13 7 " Fire Protection Program," Revision 6, and TPP 13 2," Plant ilousekeeping," Revision 2 Description of Changt, Test.14ptrJmtn1 Procedures TPP 17-7 and TPP 13 2 were revised to modify the requirements for using fire treated wood in the plant.

\

S.ununary of Safdy.D aluallan These changes do nct increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The use of only fire treated wood in the plant is not i required by NFPA 803, Section 16, and NFPA 241 codes for a plant that has been permanently I closed and is performing construction / demolition adivities. These changes do not afTect any plant equipment or the processes and procedures for responding to an equipment malfunction.

These changes are not associated with plant equipment design, operation, or maintenance and will not result in any degradation in the reliability of structures, systems, or components.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or Basca. The volume of wood in the plant is accounted for by the transient combustible program and is controlled such that the volume will not create a significant fire hazard. It was detennined that the use of non fire treated wood in the plant does not effect the conclusions in the Fire llazards Analysis for the plant in POE 1012 " Trojan Nuclear Plant Fire Protection Plan " These materials do not represent a significant fire hazard. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

12 n .

199710 CFit 50.59 Annual 1(cport Safety Evaluatinn Number 97 003 Suldtti DPMit 97 003, DCP 1," Modify Air Systems in Containment"

[

11ntdp11an.utchangrJntdhtterimsnt This modification isolated instrument air to Containment and consolidated service air to support

( decommissioning efforts. The reactor cavity sump pump air supply, fonnerly provided by instrument air, is provided via service air hose, when required. DSAlt, Figure 5.3 2, was revised _ _

to indicate a generic air supply for the reactor cavity sump pump.

SuntuuttnnLSafttLilsluallan These changes do not increase the probability of occurrence of, or consequences from, an

[ accident prev!ously evaluated in the DSAlt. None of the affected components are required to suppon the safe storage ofirradiated fuel. These changes do not result in any degradation in the reliability of structures, systems, or components.

{

These changes do not affect the margin of safety as defined in the Trojan Technical

( Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAlt,(2)

( a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced, b

[

[

( 13

[

i . ., , . . . . . . , , . - . . . . . . . . . . . ,, -

199710 CFR 50.59 Annual Report Safety EvaluationEulubu 97 007 Subjtd DPMR 97 006, DCP 2 " Modify Active Systems to Support Decommissioning Activities in the Pipe Facade ( Area PP2 3)"

Durrhttion of Changtalcal.lhntrhntal DPMR 97 006, DCP 2, removed active system in:erferences in support of DWP 00012 (elevation 63 foot pipe facade). Specifically, the Component Cooling Water (CCW) Emergency Nitrogen System was deactivated. DSAR, Section 3.3.3.2, and Figure 3.3 2, were revised to delete specific reference to the nitrogen bottles.

Sununary of Saftty Es alunlinn Th: CCW Emergency Nitrogen System was determined to no longer be required to support CCW System operations for several reasons: 1) the normal nitrogen system has proven to be historically reliable,2) adequate time is available for repair of the normal nitrogen system, if a problem were to occur with the CCW System out of service, and 3) a temporary anangement of nitrogen bottles could be set up to supply the system, if necessary. Deactivation and removal of the nitrogen bottle rack and tubing cleared a path for material flow out of the facade area, which mskes decommissioning of the area more efficient. Operation of the CCW Emergency Nitrogen System is not credited in any DSAR scenario. Removal of the system does not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The changes do not affect the spent fuel pool cooling function of the CCW System, These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR.

I These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR, (2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DS AR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

14

199710 CFR 50.59 AnnualItcport SafttLLAlualluidunther 97 008 Subject DPh1R 97 007, DCP 1," Disconnect the Clean Itadioactive Waste livaporator from Active Plant Systems and Install Access Opening into the Radioactive Waste livaporator Room" 11racrhitlettoLChangcJestublicthurnt This DPMR installed caps on piping frorn active plant systcms connected to the clean raJioactive waste evaporator. These connections included the clean radioactive waste lines to and from the evaporator, the primary makeup water supply to the evaporator, the naporator vents connected to the vent collection header, and the instrument air line to the evaporator. An access opening was created through the north wall of the livaporator Room to allow material removal. DSAR, Figure 5.2 1, was revised to remove connections to the vent collection header from the clean radioactive waste evaporator.

Sunuunty oLSafc1Ehaluation These changes do not increase the probability of occurrence of, or consequences of, an accident previously evaluated in the DSAR. The subject connections are not required or credited in any DSAR accident scenarios. No new accidents scenarios are created by these changes. The changes do not affect cooling of the spent fuel pool. Installation of a cap on the primary makeup water piping increases reliability of the system. These changes do not adversely impact any plant equipment important to safety or the processes and procedures for responding to an equipment malftmetion. These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR.

These changes do not alTect the margin of safety as denned in the Trojan Technical Speci6 cations or llases. Therefore, these changes do not involve an unreviewed safety question because,(I) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as denned in the basis fo* any technical specincations is not reduced.

15

199710 CFR 50.59 Annual Report S1ft1LEralualldumhtr 97 009 SRblttt DWP 00003, Disconnect and Rernove Equipment from the 'll' RilR Pump and lleat Exchanger Rooms" Drittintion_oLChange.lcali.Estrhurn!

This DWP disconnected and removed equipment from the 'B' RilR lleat Exchanger and Pump Rooms on the Auxiliary Building five foot elevation. PGE 1012," Fire Protection Plan,"

Table 3.51, was revised to delete reference to the RilR Room smoke detector.

SummatrofEnftty Evalunilun These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. These activities do not increase the combustible loading in the area of the spent fuel pool or change the inherent fire resistance in the pool's design. The subject rooms contain no combustible loadiiig following completion of these removal activities. Thus, the smoke detector vas determined to be unnecessary. These changes i

do not result in any degradation in the reliability of structures, systems, or components credited i

in the DSAR. None of the affected components are required to support the safe storage of irradiated fuel.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or Bases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malftmetion of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety ar defined in the basis for any technical specifications is not reduced.

16

199710 CFR 50.59 Annual Report Safety EvaluatinnEumhtr 97 010 Subjtti DPhiR 96-028, DCP 1," Spent Fuel Pool Rack Removal" Description of Change. Test Eiptrhutnt This DCP removed one empty spent fuel rack to provide access to the spent fuel pool floor for remote vacuuming. DSAR, Sections 3 and 4, were reviseJ to indicate changes in the number of available cells in the spent fuel pool and add a statement on the impact of rack removal.

POE 1037," Spent Fuel Storage Rack Replacement Report," was revised to document the plant's current decommissioning status and historical nature of the report.

Smamary of Safett Evaluatinn These changea do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The rack removal was performed using the same basic technique that was used to installit, with the exception of using divers. This technique was evaluated by the Commission in the Safety Evaluation Report for the previous re rack in i

1985. Trojan Calculation TC 751, analyzed that no damage to the fuel or spent fuel pool liner resuhed from a dropped load and concluded that the rack could be removed without creating a significant hazard to the safe storage of spent fuel, hiovement of the rack was restricted such that a postulated drop of the rack did not impact a rack containing fuel. No fuel was moved during this activity. Water displacement during this activity did not reduce the pool level below that required by TS. Rigging and special lift fixture were designed, tested, and rated as required by NUREG 0612. Administrative controls in place significantly reduced the probability of an accident. These changes do not result in degradation of the reliability of structures, systems, or components credited in the DSAR.

These changes do not afTect the margin of safety as defined in the Trojan Technical Specifications or Bases. Therefore, these changes do not involve r.n unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction ofequipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

17

199710 CI'It 50.59 Annual 1(oport SaftbitaluullonEumhcr 97 013 Suldtc1 y Rated 1.oad Test on Fuel Ilullding Crane I. 202 L

Dncdallon.nLChangeuTutdhordmrnt A rated load test and inspection was performed on Fuel fluilding crane I. 202 after the main hook and main hook yoke were machined to permit the installation of a roller type thrust bearing.

Summarv of Fafety 13 atuallon These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. Load testing increases its reliability and, therefore, reduces the probability of occurrence of a malfunction of equipment important to safety. The test did not involve handling or moving fuel. The change does not result in any degradation in the reliability of structures, systems, or components credited in the DSAR.

k These changes do not afTect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety quedion

[ because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equiprnent important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis fbr any technical specifications is not reduced, f

{

l 4

18

199710 CFR 50.59 Annual Report SaftlLEudvallonEninhrr 97 014 Suhjtti Program Changes to Establish a Radioactive Waste Processing Facility in the Condensate Demineralizer l'uilding Ilutriplian of Changc. Test. Enterlmtal A radioactive waste processing arec was established in the Condensate Demineralizer !!uilding.

The area is used to decontaminate various materials (equipment, piping, concrete, etc.) and repack radioactive waste boxes to minimize shipment volume. A separate arcu in the building was established for cutting operations. Processing in the building is predominantly dry material.

No liquid effluent stream was created. The building's ventilation exhaust path was modified to contain llEPA filtration and sampl;ng capability to comply with the Radiation Protection Program. Revision was made to the DSAR, POE-1012. " Fire Protection Plan," PGE 1060,

" Permanently Defueled Emergency Plan," PGE 1061," Decommissioning Plan,"and PGE 1012, "Offsite Dose Calculation Manual," to facilitate the change and any potential radioactive release paths.

Suminarv of Saftt y Evalualhu These changes do not increase the probability of occurrence of, or consequences of, an accident previously evaluated in the DSAR. Procedural controls ensure a low combustible load in the building. Although a new radioactive waste processing area and potential effluent path is created, the likelihood of releas- is not increased since the probability of a fire is not increased.

Consequences of a limiting radiological event (fire) fall within existing dose / release limits. No change in efnuent type will take place, llEPA filtration and sampling capability is incioded in the Condensate Demineralizer !!uilding ventilation system to filter radioactive particulates and monitor the effluent release patt Any liquid that collects in the facility will be sampled and, as appropriate, processed prior to release. These changes do not affect any plant equipment important to safety or the processes and procedures for responding to an equipment malfunction.

These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malftmetion of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of screty as defined in the basis for any technical specifications is not reduced.

19

199710 CFR 50.59 Annualitepart Saftly.fral.uallon Numher 97 015 finhjtti Trojan Plant Procedure (TPP) 14 9, Revision 3. " Control oflleavy 1.oads" lhitri!111mLuffhanulcit.Ixtterlmtn1 The Revision documented the acceptability of temporarily removing the Fuel Building crane electrical limit switch trip bars for the trolley catt and west travel, and the bridge south travel, when operating the crane south of the bridge intenuediate mechanical stops. Additional procedural and administrative requirements were added to Paragraph 4.1.3 concen ing operation of the crane south of the centerline of the cask load pit.

Sumntary of Snitty Evaluation l These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAll This safety evaluation documents the acceptability of removing the electrical limit switch trip bars on a temporary and controlled basis in accordance with the provisions in Paragraph 2.4 of TPP 30 5,"Defueled Plant hiodifications Implementation." This provision allows temporary modifications to be implemented and controlled in approved Nuclear Division Procedures. This change does not alter safe load paths or the approval to deviate from safe load paths. These changes do not affect plant equipment important to safety or the processes and procedures for respondng to an equipment malfunction.

The limit switches are additional precautionary features and are not required in order for the mechanical stops to perfarm their design function of stopping crane travel at the end of the crane rails. The limitations associated v,ith movement ofloads towards the spent fuel pool are not changed. The limit switches p: ovide a back up to the mechanical stops and serve to avoid unintentional and inadvertent contact between the crane bumpers and the stops. Itawever, the additional administrative controls provided by the specific required work package instruction and the additional approval requirements from the Shift hianager and Engineering provide reasonable assurance that unintentional and inadvertent contaet of the crane bumpers with the mechanical stops can be avoided. Contact with the stops does not constitute a safety concern or concern for a load drop. These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or liases. The limitations associated with movement ofloads toward the spent fuel pool are not changed. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR, 20

_ m

199710 CI'll 50.59 Annualiteport (2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the niargin of safety as denned in the basis for any technical speci0 cations is not reduced.

(

(

(

(

(

( -

(

(

{

{

f 21

(

199710 Cl/It 50.59 Annualiteport Saftty1:valnallunEumbu 97 016 Subjtsl DPMR 97 016, DCP 1,"45 Foot Containment Roll Up Door Installation" DucrjntIDILDLChangfalhlt EADttlWIul This DPMR installed a 10 foot by 10 foot access door in the Containment wall, designated as Door #452, to allow an alternate path for radioactive waste materials going to the Demineralizer iluilding. POE 1017," Trojan Security Plan," was revised to accommadate the change.

1 SununatInLSakty Evnlun110n These changes do not increase the probability of occurrence of, or consequences from, an {

accident previously evaluated in the DSAR. Installation of the door did not generate a new source of radioactive material or cause a significant increase in the production of contaminated materials. The door is remote from the spent fuel pool and, therefore, does not impact the design or configuration of the spent fuel pool or its related makeup systems. Therefore, installation or

operation of the door does not increase the probability of occurrence of an accident related to the safe storage of spent fuel. These changes do not afTect any plant equipment important to safety or the processes and procedures for responding to an equipment malfunction. The changes do not increase the amount of material released. The criteria used for the release of materials from the existing doors are used. Only the location of the release will be different. Controls are in place to monitor and control any releases to the environment. These changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAR. The changes are bounded by the larger door installed during the Large Component Removal Project.

The door was equipped with a lock and an alarm, as required, to control access into the protected area prior to making the final opening in the liner plate. Therefore, the change did not reduce the effectiveness of the Security Program.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR, (2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

22

199710 CFR 50.59 Annual Report Safttyhalua11onEumhcr 97 017 Subject DSAR Revision to Clarify llandling of Fuel Dntrictinn_oLChangcJnt&ptrintent This administrative change to Section 4.2.1 of the DSAR clarified the tenn " fuel handling activity." Other activities were perforrned in support of the spent fuel pool debris project, including staging equipment in the transfer canal and new fuel storage pit, cell cleaning and debris sorting / segregation, moving the coffer dam and process cans in the spent fuel pool and transfer canal, and other miscellaneous cleanup activities performed underwater in the pool and canal.

Suntinary olSaftly Evaluation These changes are adminhtrative in nature and do not increase the probability of occurrence of, or consequences of, an accident previously evaluated in the DSAR. These changes de not alTect any plant equipment or the processes and procedures for responding to an equipment malfunction. Routine clean up, sorting, and moving radioactive material in the spent fuel pool and transfer canal were perfonned in accordance with approved procedures, no physical changes were made to equipment. These changes are not associated with plant equipment design, operation, or maintenance and will not result in any degradation in the reliability of structures, systems, or components.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or llases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase in the probability of occunence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

23

199710 CI'It 50.59 Annual 1(cr. 1 Saftlylialuallunliulubtt 97 018 fiubjtrl DPMit 97 019, DCP 1," Installation of Deminerallier lluilding Smoke Detectors and Modification of Centainment Penetration 161W" 11ncriptionsfIhange,Itst.Ixpedment Smoke detectors were installed in the Demineralizer iluilding and Containment penetration 161 was modified for use as a duct for moving conditioned air from a portable llVAC unit.

PGE 1012. " Fire Protection Plan," res ision was approved to incorporate the changes.

Suminary.ni_Saftbltaluallun These changes do not create any new ellluent streams or new path to the environment for an existing stream. These changes ensure that,if a fire were to s. tart,it would be detected and extinguished in a timely manner and, therefbre, do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAIL The changes do not alter the administrative controls or requirements as defined in the TS. These changes do not affect plant equipment important to safety or the processes and procedures for responding to an equipment malfunction. 'lhese changes do not result in any degradation in the reliability of structures, systems, or components credited in the DSAll These changes do not affect the margin of safety as defined in the Tm.lan Technical Specifications or liases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAlt,(2) a possibility for an accident or malfunction of a difTerent type than any evaluated previously in the DS Alt is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

24

s 199710 CI'It 50.59 Annual Report

[

Saftt) Evalnallonnutalar 97 019 Subjeri DPMR 97 017, DCP 1 (Temporary Modification)," Containment Purge Exhaust System Pre-( Filter Removal" llturinfl03tnLCh angtJ.cstEnfiln1tal

( 1his change temporarily removed the pre filters on the containment purge exhaust system that were installed to decrease the loading and change out frequency of the downstream IIEPA filters.

[ SutninatLoDiafetyluluallan These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The Containment Purge Exhaust System is not

( imponant to safety. Another pre filter and a llEPA filter exist downstream. These changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. This temporary change allowed room to store the reactor vessel head during

{

replacement of the o rings. The pre filters were reinstalled after the head was placed back on the reactor vessel. These changes do not result in any degradation in the reliability of structures,

( systems, or components credited in the DSAR.

These changes do not affect the margin of safety as defined in the Trojan Technical

( Spec'~ cations or Bases. The Containment Purge Exhaust System is not defined in the Technical Spectiteations or Bases. Therefore, these changes do not involve an unreviewed safety question because, (1) there is no increase in the probability of occurrence or the consequences of an

( accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not cicated, and (3) the margin of safety as defined in the basis for any technical

( specifications is not reduced.

( .

[

(

[ 25

[

199710 CFR 50.59 Annual Report fiafety EvaluatinnEunther 97 020 huldtti DPMR 97 006, DCP 5," Chemical and Volume Control System (CVCS) Waste lloiding Tank and Pumps Disconnect" lleittlWlun offitance. Test. Exacriment This DCP installed caps on piping to and from the spent fuel pool and the CVCS holdup tanks and pumps, the holdup tank relief valve piping to the clean waste receiver tank, the supply to pumps P.215 A and II, and installed a plug in an unused instrument air line. DSAR, Figure 3.3 1, was revised to remove unused branch connections.

fiuntnianadhaftlyhaluatinn

{

These changes provides permanent, welded closures on lines that are closed by other means.

These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR by removing the reliance from administrative g controls on manually operated boundary valves. Changes to the DSAR are administrative in nature. These changes do not affect any plant equipment or the processes and procedures for responding to an equipment malfunction. These changes do not result in ray degradation in the reliability of structures, systems, or components. The piping on which these caps are installed do not provide any safety function.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or Bases. Therefore, these changes do not involve an unreviewed safety questa n because, (1) there is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created, and (3) the margin of safety as defined in the basis for any technical specifications is not reduced.

26

199710 CFR 50.59 Annual Report Saftt) DaluallonEntuhcr 97-026 Subjett DPMR 97-007, DCP 14. " Removal of Fire Detectors Ul34 and U135" D11trJntion of Cilangt. Test. Eintthntal This DCP removed fire detectors U134 and U135 and all associated conduit and cables from elevation 25 feet of the Auxiliary Building. These detectors provided smoke detection for Room 141 (the Boron injection Tank Room) and for Room 153 (the Centrifugal Charging Pump A Room). Revision to PGib1012." Fire Protection Plan," Table 3.51,is required to remove references.

SummatI.of_Saftty D atuallnn These changes do not increase the probability of occurrence of, or consequences from, an accident previously evaluated in the DSAR. The equipment originally contained in these rooms is not required to support safe storage ofirradiated fuel and was removed. As a result, the combustible loading of these rooms has been significantly reduced such that the subject detectors l are not longer required. These changes do not affect plant equipment important to safety or the I

processes and procedures for responding to an equipment malfunction. These changes do not result in degradation in the reliability of structures, systems, or components credited in the DSAR.

These changes do not affect the margin of safety as defined in the Trojan Technical Specifications or Bases. Therefore, these changes do not involve an unreviewed safety question because,(1) there is no increase :n the probability of occurrence or the consequences of an accident or malftmetion of equipment important to safety previously evaluated in the DSAR,(2) a possibility for an accident or malfunction of a different type than any evaluated previously in the DSAR is not created. and (3) the margin of safety as defined in the basis for any technical specifications is not reduced, 27

_ _ _ _ - _ _ _