|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint ML20151T5951988-08-12012 August 1988 Proposed Tech Specs,Revising Surveillance Requirements for ECCS Check Valves ML20151A0381988-07-0808 July 1988 Proposed Tech Specs Re Radioactive Gaseous Effluents & Radioactive Liquid Waste Sampling & Analysis Program ML20151U7171988-04-14014 April 1988 Revised Proposed Tech Specs Re Plant Sys,As Part of Rev 1 to License Change Application 142 ML20148K5971988-03-23023 March 1988 Proposed Revised Tech Specs Re RCS ML20148C2101988-03-18018 March 1988 Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts ML20196J9031988-03-0101 March 1988 Proposed Tech Specs Modifying OL NPF-1,removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5%.Certificate of Svc Encl ML20147E7371988-03-0101 March 1988 Proposed Tech Specs Re Containment Isolation Valves ML20149K1901988-02-17017 February 1988 Proposed Tech Specs,Adding New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity ML20149L6981988-02-15015 February 1988 Proposed Tech Specs Re Offsite & Facility Organization Charts.Util Certificate of Svc Encl ML20149H1121988-02-0404 February 1988 Proposed Tech Specs Revising Operability & Surveillance Requirements for Component Cooling Water Sys ML20147D4561988-01-15015 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organization Charts ML20195H8971987-12-24024 December 1987 Proposed Tech Specs Deleting Sections Re Fire Protection ML20237D6971987-12-18018 December 1987 Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves ML20237D6551987-12-16016 December 1987 Proposed Tech Specs Deleting Provision for Continued Plant Operation in Section 3/4.4.6.2 & Requiring Prompt Unit Placement in Cold Shutdown After Pressure Boundary Leakage Occurrence ML20236W7611987-11-20020 November 1987 Proposed Tech Specs Including Effects of Nuclear Fuel Design Changes ML20236Q2271987-11-16016 November 1987 Proposed Tech Specs,Resolving Control Room Habitability Issues ML20236P4391987-11-13013 November 1987 Proposed Tech Specs,Extending Surveillance Time Period for Verifying Control Rod Insertability During Control Rod Worth & Shutdown Margin Tests to 7 Days.Certificate of Svc Encl ML20236N3861987-11-0909 November 1987 Proposed Tech Spec,Revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs.W/Certificate of Svc ML20236N5881987-08-0606 August 1987 Proposed Tech Spec Section, Bases Correcting Section for Agreement W/Definition of Pressure Boundary Leakage ML20235W5571987-07-14014 July 1987 Proposed Tech Specs Re Solid Radwaste Sys ML20215K8381987-06-22022 June 1987 Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers ML20210B6241987-04-29029 April 1987 Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl ML20209D0251987-04-20020 April 1987 Proposed Tech Specs Re RCS Surveillance Requirements ML20206D9261987-04-0303 April 1987 Revised Tech Spec Pages 3/4 8-6 & 3/4 8-7 Re Onsite Power Distribution Sys,Per License Change Application 128 ML20206A6221987-04-0303 April 1987 Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves ML20245A2631987-02-26026 February 1987 Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria ML20211P0031987-02-20020 February 1987 Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region ML20211H4021987-02-11011 February 1987 Proposed Tech Specs Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% ML20207Q5371987-01-20020 January 1987 Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves 1999-03-18
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20196J5131997-07-29029 July 1997 Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137T9361997-04-0808 April 1997 Rev 1 to Trojan Proof of Principle Test Summary ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20137K5151997-03-0404 March 1997 Rev 0 to Trojan Proof of Principle Test Summary ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint 1999-08-05
[Table view] |
Text
LCA 230 Attachment E Page 1 of 7~
ADMINISTRATIVE CONTROLS g.
6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. --Th: minimum :hif t seev--
-nesesseey-f+e-+efe-shutdevn i; fiv:.
- b. -At-leett en: license 4-Oper: tor ch:ll be-in th Contr:1-r: m when
-filel--i:--in the-eenc40e, INSERT 1
- c. 4t-let:t tWO liGeA&ed-Oper4 tor: Chill be pr0:ent in-the-446tesi-poos
-duf409-Pe&C40e-6taFt=%ipy-+GhGdded-rGaGtGr-&hutdown and duri ng
-recovery-f+ r:::ter trip:. (deleted)
- d. -An-4nd4+kwal-qu:lified in radiation-protest 4+n pre :dut : :h:11 b0
-on :it: when fu:1 i: in the reastee. INSERT 2
- e. -A41-GGRE ALTERAT-IF < '.ar th: fatt4al- fuel leading :h:ll b
-44+44tl Oup:rvi:en uther : ifcensed,Sen40P-Reastoe-Operatoe-se
-Seafor h" atter Oper:tir Limited to Fuel H:ndling-de-ha?-n: Othe.
-coneveent- re: pen:ib44444e: during thi: OpcMt49er INSERT 3
^
- f. A Fire Brigade of at least 5 members shall be maintained onsite at certuted fnel all times. The Fire Brigade shall not include m::b:r: :( the-e 33f. crew-necessaey-for ::f: :hutd:wn Of the unit or any hand y on sh m ~
personnel required for other essential functions during a fire O@
. emergency. Fire Brigade composition may be less than the minimu:n requiremants for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absences of enduty members provided imediate action is taken to restore the Fire Brigade composition to within the minimum requirement of 5.
. g. Administrative procedures shall be developed and implemented to limit the workino hours of shift personnel who perform INSERT 4 ": fetyr:10ted functionsMi.:. , : nier rc : tire-optrat:r:, rt::t:r
-oper:ter:, he:lth phys 4ci:tt, :=iliarj- oper:ter:), and key maintenance personnel of the unit staff.
Key maintenance personnel of the unit staff are tnose personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of ::fety r: lated structures, systems or INSERT 5 'componentst and who are personnel performing or imediately .
supervising the performance of suc1 activities. This applies to key maintenance personnel whether on shift or not.
Adequate shift coverage shall be maintained without routine heavy use of overtime. The baseline for determining overtime use will be a 40-hour work week when the plant i: Oper: ting. However, in the event-that unforeseen problems require substantial amounts of TROJAN-UNIT 1 6-2 AmendmentNo.ZH,h~.
-h?uct 2C; 1002 9302010214-930127 PDR ADOCK 05000344 P PUR
LCA 230 Attachment B Page 2 of 7
- m. .
I ADPINISTRATIVE CONTROLS ~
overtime to be used, or during ::t:nded-p:ried: Of :hutd:.cn fw .
refuelir4r major maintenance or major plant modificatiens, on a temporary basis, the following guidelines.shall be followed:
- a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time,
- b. An individual should not be permitted to work more than 16.
hours in any 24-hour' period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time,
- c. A break of at least eight hours should be allowed between work periods, _ including shif t turnover time.
- d. -Ex::pt during : tended :hutdeun per!0d:, the use of overtime should be considered on an individual basi's and net for the entire staff on a shift.
Any deviation from the above guidelines must be authorized by the Plant General Manager or, in his absence, Duty Plant Manager, or higher levels of management, in accordance with established
- q. ' procedures and with documentation of the basis for granting the '
1 deviation. Routine deviation from the above gu!delines is net authorized.
- h. -The Shif t Manag:r and Shif t Supervi Or :h:11 :st-h-4v -a-SeMw h : 10r Operat0r Li Onsc. Th: C ntrol Operst:r and f.::f t:At.
-Gont+e4-Op:r:ter :h:1' : ch held React:r 0;erster !.i: ente.
INSERT 6 f
TROJAN-UNIT.1 6-3. .AmendmentNo.gf u= :m , =
.- LCA 230 Attachment B
.Page 3 of 7 4
TAtt! 6.2-1 HINIM;M SM!ti CRDI COMPOSITION # $
Number for. Permanently Defueled Mode
_,,,..m.. - - - . .
"* ~ ' * " - - ~ ~ ~ - ' '
_,m."..".-. Position w sam y 4 , 2 ,- 3 n,- o .
5&6 _
5% Shif t Manager e1 l'
.g. Non-Certified Operator
.2 y l s
M 7\
' n '.i::n ed Total l
. 2 l 1.
~liiTTi'Trehnis one Required Advi N.
"Z:: n:t inchd: th: 14:n::d kni:r 5::te.- 5:r:t:r :r hnter
-Austee4eem:r '.i-it.4 :: N:1 &ndling : ;: vi:ing EE= .
- . --- ,. t. .v.e.
ei -
. . .... f. . . . w .. . 4 . 4. . 4. .a. <. ,_, a_ w_ _ _ _4 .,
- 5hift crew c::: sitica may be less than the mini:us rr;uirements ~
/
r for a pericd of time net to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to ac::medata unex;ecud absence of en-duty shift crew mechers provided imediata -
~
actica is uken to rest:re tae shift c en c:=; sition :: witt.in t.*.e mini.u:s re:uiremenu cf Table 6.2-1. This previsica d:es-not .
St-=it any shif t crew ;:sitten t: be ur=anned u; n shif t change-due -
- = an enc:=ing crew =an teing lata er absent.
- M r.e ;f :-: r:;;irst-indivhu:i: fill S; th: !:'. ;::ithn: : :ha-fili c: 57A-9::i:hn prev 44e4 : Schide:1 i: ut!!'!:d f:- bee
-:::hiens, b'h:n tats--o;4h . is us ed, S: *:- Muivalen* ;h-!!: ef .
T.;aaical Oe:if t::-i:n '.. .1 sht44-not-6t-et4Mt:d ;:nding 0:
--httrance,-ef_a-f4n:1 *..--fss4:n ;:1is' / :nt- ent en c.39'n; Se
.___.u...._.-
... e.... .
dated .
TR:JAN-UNIT 1 6-4 Acend:tentNo.52,Ji,18.)k e, . eu.e g___ . , .me.e 4 ..
e l~
k...
F
.LCA 230 Attachment B Page 4 of 7.
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS-6.3.1 Each ce:ber of the facility staff shall meet or exceed the minieu.,
qualifications of ANSI N18.1-1971 for comparable positions, except for 1 the Radiation Prote: tion Manager who shall nieet or ex:eed the qualifications of Regulatory Guice 1.8, Rev. 2, April 1987. nd (2) th: Shift T::hnit:1 ff!!::r
+ho-shall-hav: : b::heler!< d:gr:: er equiv d ent in : ;cientift:-op
-eng4eeer4ep:
end-eacly:, ef-e: P!:r,t for tr:n34+ds-and-asrMents.p14ee-with-spestf4c-tt ining -in
-6.3.2 The=0pe :ti:n: M: nager chall-held Senter Reacter Op:r:ter Li:en;e.
6.4 TRAINING 6.4.1 A-retr +4ning :r.d-replasement trairing-pro f ff
-shall-be-mintainedader-the--dir::ti:n of i Ger.iPas- or the fe: i t" staffcral M:n:ger l :nd 4e-excee44he-mdre::nt: :nd-raemendati n: Of S :tien 5.5 Of 1 5 1
-N10.1-1971 :nt 16 CfR P:et-Er INSERT 7 6.4.2 A training pre ram for the Fire Brigade shall be maintained under the direction of a General Manager and shall meet or e.xceed the requirements of Section 27 of the HFPA Ccde-1975, ex:ept for Fire Brigade training sessions l which shall be held at least quarterly 6.5 REVIEW AND AUDIT V 6.5.1 PLANT REVIEV E0AR, R0 (PRB)
FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the Plant General Manager on all r.atters related to nuclear safety.
L i
l l
l t- .
i l
l v' - TROJAN-UNIT 1 6-5 ' Amendment No. 18, 31, #2, 56, If , I.45 253, I6I, IEI, T
-Augu n 20, 1:::
A_
r LCA 230 Attachment B Page 5 of 7 '
f
[
i
.g
@ lN!$1RATIV! CCNTROL5 COM90517]DN .
6.5.1.2 The PR3 sh." 'e composed of six designated sacers, including the by the Chairman. Mancers and sne Chairman shall be designated ir, writir;ing Plant General Manager. The mesters shall represent plant engineer cperations, taintenance, radiation pectection/ health physics and quality .
assuranCt.
The Chairman shall havt an academic degret in an enginetring of scienct f!ald A cr' equivalent, and, in addition, shall- have 10 years of power plant experience of whier 3 years shall te nuclear power plant experience. The other setters M-(and any alternates) shall have an academic degree in an engineering or science field or equivalent and, ir hddition, shall have a sinfeum of 5 years i techr'icitl experience of which a minimum of 3 years shall be in ene er scre of the areas listed abeve. Membe'rs without an applicable acadt!.ic degree shall l i
have a siniews of 10 years technical experience, of which a minisue of 3 years '
shall.be in one er m:rt of the areas listed abovt. It h:st==:
c..t.. n...+.. n ...... es...g cf it: c4 y ge,en-g g g gg_gg.n u u .
ALTERNati$
' 6.5.1.3 All alternate sembers shall be appointed in writing by the Plant A-
,e General Manager to serve en a temperary basist however, no scre than two .'
alternates shall participate as voting macers in PRI activities at any one .
time.
HEETIN* UE U! Q 6.5.1.4 The PR! shall eeet at leas . ence per calendar a: nth and as convened by tne PRS Chairman er his designated alternate, CUORUM 6,5.1.5 A qw: rum of the PRS shall c:..sist of the Chairman er his d-signated alternata and at least four mem:ers including alternates.
RESPCN$iSILITl!3 6.5.1.5 The Plant Review Board shall be responsible for:
- a. Review of the safety evaluations for: - (1) procedures, (2) change to precedures, equipment, systems er f acilities, and (3) tests er "
experiments complettd under the provision of 10 CFR 50.59 to verify that such actions did act ccnstitute in unreviewed safety question..
- b. Review of proposed procedures and changes to piccedures, equipeent, systems or facilities which may involve in vr. reviewed safety question as cefined in 10 CFR 50.59 ce involves a change in Technical Specifications.
6-6 Laencent he. #2.128,I3!, yo, g ^
TEO.4 . UNI
1
~
. . LCA 230
~ '
Attachment B Page 6 of 7 ADMIN 15TRAT1YE CONTROLS f-i*
6.8.3 Temporary changes to procedures of 6.8.1 may be made provided:
- a. The intent of the original procedure is not altered.
- b. For procedures covering activities performed by the Facility Staf f, the change is approved by two members of the Plant is a . 2rtified Management Staf f, at least one of whom holds a Senior Reacts fuel : indler . ope'r44oris-L4 cense er Tr+}w, and the change is documented, reviewed, and approved by the Responsible Manager within fourteen (14) days of implementation,
- c. For procedures covering activities performed by Company organizations other than the Facility Staf f, the change is reviewed and approved in accordance with the Nuclear Quality Assurance Program.
h 6.8.4 The following programs shall be established, implemented, and maintained:
- a. Primarv Coolant Sources Outside Containment A program to reduce leakage from systems outside Containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical-levels. This program shall include the following:
(i) Provisions establishing preventive maintenance and periodic visual inspection requirements, and (ii) Leak test surveillance requirements for each system at refueling cycle intervals (18 months).
- b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentratiers in vital areas under accident conditions. This program shall include the following:
(i) Training of personnel, (ii) Procedures for monitoring. and (iii) Provisions for maintenance of sampling and analysis equipment.
- c. Secondarv Water Chemistry A secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
(i) A sample schedule and control points for critical parameters.
(ii) Use of connonly accepted industrial procedures for quantifi-cation of parameters that are critical to control points. ((
TROJAN-UNIT 1 6-14 Amendment No. 78, 27, (2, 77, 97, 70f M -e,6111 tar n asc+
_ . . - . . . _ . - . - - -..... .. . . ~.
ll: 9 _ ?*
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'# LCAL230 ~
_ Attachment BE Page 7Eofs7 lasatt_1 i At least one individual qualified to stand watch in the control-room (non-certified operator or 6 certified fuel handler) shall be in~the control-room when fuel is in the spent fuel pool.
inantL_2 s An individual qualified-in radiation protection procedures-shall be onsite during' fuel handling operations. .
Insert 3 All fuel handling operations shall be'directly supervised by a' certified fuel handler.
InsatL_4 important to the safe _ storage of irradiated fuel assemblies (i.e.,
certified fuel handlers, radiation protection personnel, non-certified !
operators)
Inacti_5 Important to the safe storage of irradia;ed fuel asseniblies .
.in.sacL6.'
The Shift Manager shall be a certified fuel handler. /u1 operator holding; a license as a Senior Reactor Operator in accordance with 10 CFR.55 is:a certified fuel handler.
-Inaert_Z c A NRC-approved retraining and replacementitraining program-for-the-certified fuel handlers shall"be maintained under the' direction of a General Manager.
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!: 'SAB/bsh 7416W.0193
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