|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp ML20137B9371997-03-18018 March 1997 Proposed Tech Specs,Revising TS Section 5.3.1,fuel Assemblies to Allow Use of Alternate Zr-based Fuel Cladding Matl ZIRLO ML20137B9141997-03-18018 March 1997 Proposed Tech Specs,Revising TS SR 4.5.2.c to Clarify When Containment Entry Visual Insp Is Required ML20134Q0811997-02-17017 February 1997 Proposed Tech Specs,Revising TS 1.7, Containment Integrity, TS 3/4.6.1, Containment Integrity & TS 3/4.6.3, Containment Isolation Valves 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20207J9621998-12-18018 December 1998 Rev 1 to TRM for Wolf Creek Generating Station,Unit 1 ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20195E7671998-11-10010 November 1998 Rev 0 to EPP 01-2.4, Core Damage Assessment Guidance ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20138F3371997-04-30030 April 1997 Rev 0 to Offsite Dose Calculation Manual ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp 1999-09-02
[Table view] |
Text
1 l
Attachment IV to ET 91 0040 14ge 1 of 7 l
l l
l l
ATTACIMENT IV l'R01'O$t:D TICilNICAL SI'!:CIFICATION CilANGP.S l
910305o23o 939 ,
l- hDR ADOCK os;o$$ 02 l- PDR f
_ _ _ _ _ ~ - _ . -_ - _ .._ _ _ _ _ _ _ _ .__._. _ _ . _ _ _ ._ _ _ . _ _ _ . _ _ _ _ _ ,
Attachment IV to L191-0040 Page 2 of 7
. ADMINISTRATIVE CONTROLS l l
Unit Staff (Continued)
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition while the Unit is in HDDE 1, 2, 3 or 4, at least one licensed Senior Sperator shall be in the control room; 1
- c. An indbidual from the Health Physics Group *, qualified in radiation I proteLion procedures, shall be on site when fuel is in the reactor;
- d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; .
- e. A site Fire Brigade of at least 5 members' shall be enintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor, and the two other members of the minimum shift crew necessary for safe shutdown of the Unit and any personnel required for other essential functions during a fire emergency; and
- f. Administrative procedures shall be developed and implemented to limit the working hours of Unit Staff Uo perform safety related functions; e.g., Senior Operators, Operators, Health Physicists, Auxiliary opera-tors, and key maintenance personnel.
The amount of overtime worked by Unit Staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 8212),
- g. Th d,e 4pe+e-t4em Lpegi3ee shall hold a senior reactor operator license,
@rvisor Operatforis or Manager Operattop
'May be less than the minimum requirements for a period of tirne 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 accommodate unexpected absence provided immediate action is taken to fill the required positions.
WOLF CREEK - UNIT 1 6-2 Amendment No.24
Att6thment IV to El 91-0040 Page 3 of 7 i . T ABLE 6.21 MINIMUN SHIFT CRrw COM005!110N 0051110N NUMB (R OF IND!vlDUALS RtQUIRED 10 flLL P051110N MODE 1, 2, 3, or 4 MODE 5 or 6 l
$$ 1 l' SR0 1 None R0 2 1 50 4 1 STA 1** Noet CHM 1 None 55 - Shift Supervisor with a 5 enter Operator license on Unit 1 l SRO -
Individual with a Senior Operator license on Unit 1 '
RO: - Individual with an Operator license on Unit 1 50 --
Station Operator STA -
Shift Technical Advisor CHM - Chemistry-Personnel-The Shift Crew Composition may be one less than th'e minimum requirements of Table 6,2 1 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 accommodate unexpected absence of on duty shif t crew members provideo immediate action is taken to restore the Shift Crew Composition to within the minimum requirements i of Table 6.2*1. This provision does not permit any shift crew position to be unmanned upon-shit. change due to an ontomino shift crewman being late or absent, Q perv1s'ing Operator 3 -
' During any absence of the-0M't Wp;r,1;;r froni the control room while the unit is in MODE 1, 2, 3, or _4, an individual (;th;r th;r. th; Shif t ie:hricel Ani;;r)- with a-valid Senior Operator license shall be designated to assume the control *oom command function. During any absence of the Shif t Super ieer -
'from the control room while the Unit is in MODE 5 or 6, an individual with a .
valid Operatrr license (;th;r ther, the Shif t ishr. ice; miser) shall be designated to assume the control room command function.
Qupery5ingUp .
I 'One $RO, either $hif t Supervisor or Supervising Operator.
"The:5TA position shall- be manned in MODES 1, 2,: 3, and 4 unless the Shif t Supervisor or the individual with a Senior Operator license meets the
- qualifications for the STA as required by the NRC.
c WOLF CREEK UNIT 1 65 i-
. . . - o 4. ......m_.....m.._..,_.-..,,,_...m., ._,_,...~.._._,m..... ,,,_,m.__,,,,,,,...,_,~,,._ -.,.,v_,m . _ , , , , ,
Attachment IV to E19100@
Page 4 of 7 ADMIR157RATIVE CONTROLS
- 6. 2. 3 1NDtPINDENT SAFETY [NGINfERING CROUP (!$(G)
FUNC110N .
6.2.3.1 NRC issuances, industry advisories, REPORTABL[ [ YEN 15 and plant cesign and operating experience information, including plants of similar design, which may indicate areas for improving plant safety. The 15EG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Chairman Nuclear Safety Review Committee.
COMPOSITION 6.2.3.2 The on neers located ISEC site.shall be composed of at least five, dedicated, full time engi-Each shall have a bachelor's degree in engineering or related scien;e and at least 2 years professional level experience in his field.
Resp 0N51BILIT![$
6.2.3.3- The 15EG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are cerformed correctly and that human errors are reduced as much as practical.
RE*0RD$
(7 6.2.3.4 r toined, and forwarded each calendar month to Chairman Nuc?e Committee.
- 6. 2. 4 SHIFT TECHNICAL A0V150R The Shif t Technical Advisor (STA)" shall provide technical support to the Shif t -
Supervisor in the areas of ther'tal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the Unit. "
- 6. 3 UNIT STAFF OVAt.!FICATIONS -
nsert A M 14t:5 :-1:e :f th: 'Jn&t-44af4 -:~; .
H44en: ::et-+r-e4*d the e!"Ne quM444*
th:1' meet-ee-t*ceed th; wt4444c+ Hee-of-Re9detony LS, 0:pt::L r W hid:O 6- f ' M E ! ," N T*.6 J',+c nsee4por+t+rW the '!RC + shaL1 tet er ese64-the-r44uir4msnts of AM5!"NS41-195L l
w: 4W14f4 sat 46h&-+f-the-64pplempt44-r+wirempts 4p+tified 'a:nd $ r46r-Oper4 to S--of En:1Mvet- 1 of th "a.et h 2 B , 49&O-4404&4440.- t e e ! ' ' i c t a ' e t !!: t.
tion:
'Not responsible for sign off function.
"The STA position shall be manned in H0 DES 1 Supervisor or the individual with a Senior Operator license meets the, 2, 3, and 4 unless qualifications for the STA as required by the NRC.
WOLF CREEh UNIT 1 6-6 Amendment No. f U , 14
.,..m._m ...
Attachment IV to ET 91 0040
- Page 5 of 7 Innert A i
6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /AN$ 3.1 1978 with the following erceptions:
- a. Licensed -Opert. tors and Senior Operators shall meet or exceed the ,
qualifications of ANSI /ANS 3.1 1981 as endorsed by Regulatory !
Guide 1.8, Revision 2.
- b. The position of Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
- c. The NSRC members shall meet or exceed the requirements of ANSI /ANS 3.1 1981.
Attachment IV to L1 91-0040
,Page 6 of 7 5
ADMINISTRATIVE CONTROLS e - __
98um
- 6. 4 TRAINING c
CInsert B
-~
+
- 2.--.Aanr-64*4+g-s*d +ep4ecenet4e4*ing-4ppr4m-fw-the wbt-+4+f4-+h644
-t+ 444nt44Aeo-94 dew-tJ.e-4k+c4A+n-+f4ho4ren4Ag-J4anager-e4-+bo44-n+et-en---
wue - t he - r eq u ! r+ net tr- end--recernende t4c nt-o f4ec440n-4-of-A N S4/AN Er--3+1970 And Append!' "'" o f40-CM-AeM45-*ed-+he-+vppl+mento4-*Mtuh* ment 1- tN ci lied i~ h: tie- ^ end- C-4f=-Enc 4ptrure4-of--the-Mec4t-28r-19BO-NRC-4+tieeto-eI+
44ee*:e:0, Ond-she444nehde4emH4er+ ret 4en-*ith-relevant--4edustry-epere14en64
++ee4enet - i de n t i44td-by-the-MEfr- or-enother- phot group.
6,5 REVIEW AND AUDIT
,6. 5.1 PLANTSAFETYRQlEWCOMMITTE_E(PSRC)
FUNCTION 6.5.1.1 The PSRC shal) function to adviso the Plant Manager on all matters related to nucitar safety, ,
COMPOSITION 6.5.1.2 The PSRC shall be composed of the:
Member: Manager Nucleer Plant Engineering Wolf Creek Member: Manager of Operatichs l Membe r: Manager of Technical. Support Member: ' Manager of Maintenance and Modifications Member: Manager Instrumentation and Control Membe r: Reactor (ngineering Supervisor Member: Health Physicist Member: Chemist Memta r: Results Engineering Supervisor Chai rn,a n: Manager of Plant $upport ALTERNATES 6.5.1.3 Al'i 6) ternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary ba, sis; no.ever, no more than tWo alternates shall participate as voting members in PSRC activities at any one time.
i wolf CREEK Unli 1 6-) Amendment No. 20, 25 z
- - - - . . . . . - . - - ..- .. - _ . - - . ~ -. . . - - . . - , . .- ,
~
/
l Atte.chment IV to ET 01 0040 f> age 7 of 7 Insert B 6 4.1 A retraining and replacement training program for the unit staff shall be maintair.ed under the direction of the Manager Training and shall meet or exceed the requirements and recommendations of Sectich
- of AN61/ANK 3.1 1970 with the folloving exceptions:
- a. Tho training program for Licenami operators au t Senior Operators shall meet or exceed the requirements and t a comnmndations of Section $ of ANSI /ANS 3.1 19Al as endorsed by Regelatory Guide 3.8, Revision 2, and 10 CcR I' art $5.
- b. Training shall include femiliarization with relevant itidu s t r y 3,
operational experAence identified by the ISEG or another plant 3roup.
I
4
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