|
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K0641999-09-0101 September 1999 Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6 ML20211G7681999-08-27027 August 1999 Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP ML20196E2191998-11-30030 November 1998 Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves ML20195K3831998-11-20020 November 1998 Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7181998-11-19019 November 1998 Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20155F7001998-10-30030 October 1998 Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant ML20154N1961998-10-16016 October 1998 Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S5621998-07-20020 July 1998 Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20217D2691998-04-21021 April 1998 Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging ML20216H0831998-03-16016 March 1998 Rev 13 to Proposed TS Re Conversion to Improved TSs ML20199J5281998-01-28028 January 1998 Proposed Tech Specs,Converting to Improved TSs ML20198K9851998-01-12012 January 1998 Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432 ML20198R7331997-11-0505 November 1997 Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS ML20217K6161997-10-23023 October 1997 Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs ML20217K6671997-10-22022 October 1997 Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20198K3321997-10-20020 October 1997 Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs ML20217G3571997-10-0606 October 1997 Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS ML20217G3781997-10-0606 October 1997 Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS ML20211J2751997-10-0202 October 1997 Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20217C7361997-09-29029 September 1997 Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs ML20210T8701997-09-10010 September 1997 Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel ML20210K9711997-08-14014 August 1997 Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel ML20149H5821997-07-21021 July 1997 Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432 ML20148P7171997-06-27027 June 1997 Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20135F0441997-03-0606 March 1997 Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves ML20134E3361997-02-0303 February 1997 Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request ML20134E3221997-02-0303 February 1997 Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request ML20134D3041997-01-31031 January 1997 Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging ML20135A5231996-11-26026 November 1996 Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20134N1831996-11-20020 November 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML20128H6031996-10-0303 October 1996 Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7991996-09-10010 September 1996 Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys ML20117L3441996-09-0404 September 1996 Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01 ML20116F8281996-08-0101 August 1996 Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation ML20116E3771996-07-26026 July 1996 Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving ML20117F6431996-05-15015 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls ML20101K6011996-03-28028 March 1996 Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient ML20096D4461996-01-16016 January 1996 Proposed Tech Specs,Adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095K2761995-12-21021 December 1995 Proposed Tech Specs,Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 ML20095C7471995-12-0707 December 1995 Proposed Tech Spec to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant ML20094S1531995-11-30030 November 1995 Proposed Tech Specs,Allowing Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20094D6171995-11-0101 November 1995 Proposed Tech Specs,Upgrading ESF Electrical Sys at Plant to Provide Addl Protection from Loss of Electrical Power ML20093M4291995-10-20020 October 1995 Proposed Tech Specs,Extending 18-month Surveillances to 960331 ML20098C0741995-10-0202 October 1995 Proposed TS 3.7.6.1,extending Action Statements a & B from 7 Days to 30 Days for Loss of Emergency Power ML20086N2551995-07-13013 July 1995 Proposed TS 5.2.1, Fuel Assemblies, Allowing Use of Cladding Matls Other than Zircaloy or ZIRLO W/Approved Temporary Exemption to 10CFR50.46,10CFR50.44 & 10CFR50,App K & Allowing Use of Lead Fuel Assemblies ML20085D5091995-06-0909 June 1995 Proposed Tech Specs,Implementing Changes to Radiological Effluent TS Per GL 89-01 ML20084R0171995-06-0606 June 1995 Proposed Tech Specs Reflecting Extension of Certain 18-month Frequency Surveillances to Refueling Interval ML20084P9741995-06-0202 June 1995 Proposed Tech Specs Re Pressurizer Safety Valves Lift Tolerance ML20087H9281995-04-28028 April 1995 Proposed Tech Specs Re Extension of Allowed Outage Time ML20081D0551995-03-15015 March 1995 Proposed Tech Specs Re Reformation of Current Administrative Controls Section of Plant TS & Relocation of Several Requirements to Other Documents & Programs 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K0641999-09-0101 September 1999 Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6 ML20211G7681999-08-27027 August 1999 Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP ML20207F0261999-06-0101 June 1999 Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2 ML20195B2751999-03-31031 March 1999 Rev 0 to Rept 98-FSW-021, Corrosion Test of SG Tubes with Alloy 800 Mechanical Sleeves ML20204H6011999-01-29029 January 1999 Age Related Degradation Insp (Ardi) Program Technical Requirements Document for Mechanical Systems ML20196E2191998-11-30030 November 1998 Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves ML20195K3831998-11-20020 November 1998 Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7181998-11-19019 November 1998 Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20155F7001998-10-30030 October 1998 Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant ML20154N1961998-10-16016 October 1998 Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20198A2981998-09-15015 September 1998 Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry ML20198A3131998-09-15015 September 1998 Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated ML20236S5621998-07-20020 July 1998 Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20195B2861998-06-0505 June 1998 Rev 0 to Rept 98-TR-FSW-005, Test Rept on Alloy 800 Mechanical Sleeve-Addl Qualification Testing Using Low Yield Strength Tubing ML20217D2691998-04-21021 April 1998 Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging ML20216H0831998-03-16016 March 1998 Rev 13 to Proposed TS Re Conversion to Improved TSs ML20198A2911998-02-23023 February 1998 Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System ML20199J5281998-01-28028 January 1998 Proposed Tech Specs,Converting to Improved TSs ML20198K9851998-01-12012 January 1998 Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432 ML20198R7331997-11-0505 November 1997 Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS ML20217K6161997-10-23023 October 1997 Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs ML20217K6671997-10-22022 October 1997 Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20198K3321997-10-20020 October 1997 Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs ML20217G3571997-10-0606 October 1997 Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS ML20217G3781997-10-0606 October 1997 Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS ML20211J2751997-10-0202 October 1997 Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20217C7361997-09-29029 September 1997 Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs ML20211J2981997-09-18018 September 1997 Pump & Valve IST Program Third Ten-Yr Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20210T8701997-09-10010 September 1997 Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel ML20210K9711997-08-14014 August 1997 Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel ML20149H5821997-07-21021 July 1997 Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432 ML20148P7171997-06-27027 June 1997 Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20141G4471997-06-16016 June 1997 Ccnpp Unit 2 Cycle 12 Startup Testing Rept ML20141D9341997-05-0909 May 1997 Radiation Safety Procedure 1-104, Area Posting & Barricading & High Radiation Area Pre-Entry Checklist ML20135F0441997-03-0606 March 1997 Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves ML20134E3221997-02-0303 February 1997 Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request ML20134E3361997-02-0303 February 1997 Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request ML20134D3041997-01-31031 January 1997 Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging ML20210P3971996-12-0404 December 1996 Rev 2 to RP-2-101, Administrative Procedure Radwaste Mgt ML20135A5231996-11-26026 November 1996 Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20134N1831996-11-20020 November 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML20210P3871996-10-17017 October 1996 Rev 2,Change 0 to Offsite Dose Calculation Manual ML20128Q8041996-10-14014 October 1996 Cycle 13 Summary of Startup Testing ML20128H6031996-10-0303 October 1996 Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7991996-09-10010 September 1996 Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys ML20117L3441996-09-0404 September 1996 Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01 ML20116F8281996-08-0101 August 1996 Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation ML20116E3771996-07-26026 July 1996 Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving ML20117F6431996-05-15015 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls ML20101K6011996-03-28028 March 1996 Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient 1999-09-01
[Table view] |
Text
_ _ _ _
NI'TACBeir 1 h3~ N
,m
,Y PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTION:
- a. Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
- 1. Either decontaminated and repaired, or
- 2. Disposed of in accordance with Cc= mission Regulations.
(~N L./'
- b. The provisions of Specifications 3.0.3 and 2.0.4 are not appli-cable.
SURVEILLANCE REOUIREMENTS 4.7 9.1.1 Test Recuirements - Each sealed source shall be tested for leakage and/cr contamina: Ton by:
- a. The licensee, or
- b. Other persons specifically authericed by the Commission or an Agreement State.
l De test methed shall have a detection sensitivity of at least D. DOS--r^-
tehydamn microcuries per test sample. i//gg i
.as (w
4.7.9.1.2 Test Frecuencies - Each category of sealed sourcesp tested t tne frequencies cescribed below. A
- a. Sources in use kxcluding st+r4tte-sett ~:-es ;nd 'i--kn d:tC t:r; preficuslt s uW4ed-to-eerc el t;x ) - At least once per six
() 8305060405 830427 montns for all sealec sources ccntaining radioactive material:
PDR ADOCK 05000317 P PDR CALVERT CLIFFS-UNIT 1 3/4 7-63 M & rr Ib l
x _
J[f 93-46 ATTAC995ff l'(Cont'd) p ..
M .
PLANT SYSTEMS h. '
v.
SURVEILLANCE REOUIREMENTS (Cokinued) 3, n
- 1. With a half-life! greater than 30 days (excluding Hydrogen 3),and 4'
- 2. In any form othe/ than gas.
T~
- b. Stored sources not in use - Each sealed source and fission .
cetector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
- c. Startuo sources and fission detectors - Each sealed startup days source prior to being and fission subjected detector to core shall begsgggny%
flux cau a ro.6vw n3 pair or y
maintenance to the source or detector.
4.7.9.1.3 Reoorts - A report shall be prepared and submitted to the a Comission on an annual basis if sealed source or fission detector W leakage tests reveal the presence of > 0.005 microcuries of removable contamination.
O CALVERT CLIFFS-UNIT 1 3/4 7-64 j mod-id #c.
_ --__ _ _ _ - - - . - 1
~ ..
93-%
'. ATTACIMNr 1 (Cont!d)
' PLANT SYSTEMS
() 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING C0"DITICN FOR CPEP.ATION 3.7.9.'l Each sealed source containing radioactive material either in excess of 100 micrecuries of beta and/or gamma emitting material or 5 microcuries of Eipba emitting material snail be free of > 0.005 microcuries of removable centamination.
APPLICABILITY: At all times.
ACTION:
- a. Each sealed source with removable centamination in excess of the above limit snall be immediately withdrawn from use and:
? 1. Either deconta=inated and reDaired, or
- 2. Disposed of in accorcance with Ccmmission Regulaticns.
Il i b. The provisions of Specifica:icns 2.0.3 and 3.0.4 are not appli-('l -
cable.
v l
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. ..".';TC 3
4 i
! 4.7.9.1.1 Test Recuirements - Each sealed scurce snall be tested for I leakace anc/or contamina:1cn by:
i
! a. The licensee, or
.e l b. Other persens s;ecifically authcriced by the Ccemissica or an j Agreemen: State.
The test method shall have a detec:icn sensitivity of at least 0.005 microcuries per :es: sampic. em I
(e.caem stcrhp w, l' 4.7.9.1.2 Tes: Frecuencies_- Each catecerv cf sealed scurce2 rnTTT' YeT c d 6sh tested at :ne frecuencies cescrl:ed below.' , /?EEuus s5Jel*"-s g[.j>j
- a. Scurces in use n =-c -- ~ct:rtr- - - :: :nd ::::icr :; -
crem;c;;; tur-c"-=" ::re = ; c ieast once per s x mon:ns for ali seaiec sources cen airing radioactive material:
O a
CAL'/ERT CLIFFS-UNIT 2 2/c 7-55 ,
Hverinut No.
_L $3-%
ATTAClearr 1 (Cont'd)
G*(
t -
7 -,
b-( l PLANT SYSTEMS .
SURVEILLANCE REOUIREMENTS (Continued) e-i
- 1. With a half-life $ greater than 30 days (excluding Hydrogen.
3),and -
- 2. In any form other than gas.
- b. Stored sources not in use_ - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested:within the previous six months.. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
- c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tagagghjg31 ndays g prior to being subjected to core fluxfEno roi sawmg repair or maintenance to the source or detector.
4.7.9.1.3 Reoorts - A report shall be prepared and submitted to the Comission on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.
.- s CALVERT CLIFFS-UNIT 2
.'3N'7-64 Med S.
..L:h:
i O O O '.
TABLE 3.7-4 .
)
"J SAFETY RELATED llYDRAULIC SNUBBERS
E SNUBBER SYSTEM SNUBBER INSTALLED ACCESS 10LE OR HIGli RADIATION ESPECIALLY DIFFICULT E ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE NO.
E (A or 1) (Yes or No) (Yes or Ho) {
A No No 2 1-36-1 SUCTION #11 AUX. FEED PUMP 12' A No No 1-36-1A SUCTION #11 AUX. FEED PUMP 12'
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6e M O-4 RE550RIZER-S AMPLE-LINES-38' I Yes = l I Yes No i 1-38-S PRESSURIZER SAMPLE LINES 24'-
I Yes No 1-38-6 PRESSURIZER SAMPLE LlHES 37' i
((
A No No 1-24-1 DIESEL GENERATOS #12 EXilAUST 92' h '
A No No
" l-24-2 DIESEL GENERATOR #11 EXilAUST 92'
=
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x IEGEND: RO - Reactor Operator License h Tg SRO - Senior Reactor Operator Q
'Onsite Responsibility for Fire 4 Protection Pmgram w r :=
@6 TEM Figum 6.2.2 Organization Chart (Two Unit Operation) - Calvert Cliffs Nuclear Power Plant Baltimom Gas and Electric Conpany . s l
i
g, ATTACIfbh' 4 y- ,.
f-ADMINISTRATIVE CONTROLS p
. 6.3 FACILITY STAFF QUALIFICATIONS ,
)
I 6.3.1 Each member of the facility staff shall meet or exceed the minimum L qualifications of ANSI N18.1-1971 for 'ccmparable positions, except for the f Radiation Safety Engineer who shall meet or exceed the qualifications of k Regulatory Guide 1.8 September 1975, arid (2) the Shift Technical Advisor who
~
shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Supervisor for the Production Maintenance Department and shall meet or exceed the requirements and recc=mendations of Section 5.5 of ANSI N18.1-1971 and Appendix " A" of 10 CFR Par: 55, as applicable.
6.4.2 A-training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975. _
6.5 REVIDI AND AUDIT
- 6. 5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The POSRC shall *ie ccaposed of the:
Chairman: Plant Superintendent Member: General Supervisor - Operations Member: General Supervisor - Electrical and Centrols Member: General Supervisor - Chemistry Member: Principal Engineer - Plant Engineering Nuclear
[ Member: General Supervisor - Maintenance and Modifications l
Member: Principal EnE,ineer - Incore Fuel FanaEement Member: General Supervisor - Radiation Safety Member: General Supervisor - Training and Technical Services l
ALTERNATES 1
l 6 . 5 .'l . 3 All alternate members shall be appointed in writing by the POSRC l
Chairman to serve on a temporary basis; however, no more tnan two alternates l shall participate as voting members in POSRC activities at any one time.
l CALVERT CLIFFS 6-6