|
---|
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
.
- . , ( t e -
10 UC0 .-
o co
CO s O
o a, 9,r-X (r} R< Vke Pses& dent hiear Energy O CD N OQ OOn i i i i OO l Penns mas o ans Manesee Manager Manager uanager O O- [ri aWG wi 5.sesy Rev.e. haean t+ clear Engineerlas Quatley Ass nance and Nuclear Comm.tisce Opc<anksia 5.reeces 5 aff Seswkes Maanienne Q >= .n a e
g I 5*.a hsear .or
~' -
I i I I I I I I t.5 c5 c5 G5 c5 c5 G5 C5 GS Qaa44 y G5 Plant & Tedeniul G5 Plansinna CS C1 Quensty Canures Electskal g Opes as6ans RaJeasksi Clienissary Caisss4 A Destge Project Servicee Qaality aruf Nr_ lear Medankal and %ppust and Qg{ Salesy Susvus t Ea6b lat Eat ineering e q inrevina Au sance Suppost , Tr ainang. Wanneeew. ice Ser.).xs Centrois Op est.,or3 s
SRO 1 Jra i i SRO Vencesseen Shaft Developsnent & Maantenance A LEGENDS G5 - General s gnerviser(/ > 0MN '
i SRO - 5enner Reacser Operator Lkenne
$go RO - Reacter Operator Lkenee C.. ,. R w e, I
y C
., R.L Ope, a..
g The. GS-O? emh% skall hdj or kak ked an y ; SRO License ~ at Calvert Cllffs a i
e i 3 Plant Opes ase' FIGL)RE 6.2-2 O ORGANIZ ATOON CalAR T (f WO LWelT OPER ATSON)
CALVERT CLIFF 5 NUCLEAR PO9ER PLANT
% SALT 8n40RE GA5 & ELECIREC COMPAN1r M
e N e o
N, tu e <
TIG Se om o
W N
O 1 l -
. ~
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OLlALIFICATIONS
,6.3.1 Each member of the facility staff shall meet or exceed the mininum qualifications of ANSI N18.1-1971 for comparatie positions, except fc: (1)the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septemoer 1975, and (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 - Nuclear Training and shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A of 10 CFR Part 55, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Quality Control and Support and shali meet or exceed the requirements of Section 27 of the NFPA Code-1975. l 6.5 REVIEW AND AUDIT ,
6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
~
FUNCTION t 6.5.1.1 The POSRC shall function to advise the Manager-Nuclear Operations on
, all matters related to nuclear safety. l COMPOSITION 6.5.1.2 The POSRC shall be composed of the:
Chairman: Manager-Nuclear Operations l Member: General Supervisor - Operations Member: General Supervisor - Electrical and Controls Member: General Supervisor - Chemistry .
Member: General Supervisor - Mechanical Maintenance l Member: General Supervisor - Technical Services Engineering Member: General Supervisor - Radiation Safety l Member: General Supervisor - Plant and Project Engineering Me-e gN Gener.: upemfor - Bengn s :neeriv I ALTERNA"TYS 6 emM S af erm" -QuaMyAsurMe
- 6. 5.1. 3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time, m vun CLIFFS - UNIT 1 6-6 Amendment No. 26,43,33,62.25, 110
_ _ _ _ _ _ _ _ _ ._ .-~ . _.
... s .
ADMINISTRATIVE CONTROLS MEETING FRE00ENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chaiman or his designated alternate and 4ew- members including alternates.
fWe RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:
a. Review of 1) all procedures required by Specification 6.8 and. changes thereto, 2) any other proposed procedures or changes thereto as determined by the Manager - Nuclear Operations to affect nuclear safety. l
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Appendix "A" Technical Specifications,
- d. Review of all preposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical Specifications includ-ing the preparation and forwarding of reports covering evaluation and
' recomendations to prevent recurrence to the Vice President Nuclear Energy and to the Chairman of the Off Site Safety Review Comittee,
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards.
. h. Perfonnance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site S'fety Review Comittee.
- 1. Review of the Plant Security Plan and implementing procedures and shall submit recemended changes to the Off Site Safety Review Comittee.
- j. Review of the Emergency Plan and implementing procedures and shall submit recemended changes to the Off Site Safety Review Comittee.
- k. Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recamendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Manager-Nuclear Operations and the Off Site Safety Review Comittee.
- 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 26,20,A3,3A,/)9,5,110
fI l
~
~'
r o
s u
4
- W
- r e
te " ei y o b I
srk Js= ~ S L f' s ctca'- le c l r I E
r a o C e
i r r n e aa gcn aie nta e e
c I
sCp" G yk -
se re nu" t r ep 6
n e aI A P Mfa&na a itlu5 las e
M Q ua J U v AdC l
e" k" d.>
1 n >
I C te '-
t e A >
M *-- ~
n D S
r Gn aR a e Sl e d
n a
I Gc*" u N'
Ae n k
C es Le r )
4 r
e gr c e nc an f s na g '
ndn g%
r e ,i t e s k eL s
e f
A W N OI I NY MAN a s e cna a -
rp ob i
nsS u r l d6A isOo MaAf EFP l
P ' s L
ewsr f
tya -
P Ra O2o e
e
&S tn y" vt SeO cp a
- T *t C Q
a I
Sl a -
Gea -
t t
s Rw s 4s '(C UrFlu t
ng ee t e kn y
Q ^"
=
ao<
GSR rt nin a eee e 2 2
4 t
oMi t 4C i
t EE tL nE l s-T /E *.
r r l e U RN 1
u c '~
h*R Pa e S el I s. e s i iv- 5OO GI ASA t
uuc t t
tei r GR 5 R t aF C4G VN h
- g T eS s T 1 YCR 6E .
r k i
n r
e e s O
N E
G K O TTe Asi t m r
eien gan g c. se c-
&t E L
AET
n a E e.
Gnle-la es * %FS MraS e
FP"' .C J l e -
O c '
u N
st g
I 1i-Gse D "* *
. s e
a'
~ o=
sl r
el i
r
~
Icats
- e om.
n i Oe' C a n ,
]I y
MC r r w e. t s
e
. 1i Cme s
lw a,.
_sre e on n
Nsa l u
e..e ss t
gen l1 C s s a
Lus a ae , m. pt saue e n i c _.
Mf p O S l
u se-v r u eM :n.A. eu F
GeJ a5
'- D R
(j s
mre Onw e
se 1 O Se.
M. :R . 8 ltaes se es pMa s*
s a
R 1 ts e, Rn s
R, .
s 88 n*
a Og-g oe -
nl la a O_
1 6a 5 sEs (
1\ ie S.,.
s i lea s c s%
n o
C t
C_ e e,
1 l P "P O
P S -
\ -
s - A s
s -
s n
Cr - Nd nr ~';,in -
' C2~8 " ~
gv 6O 4R mew r a $ " 2O* tG,NN.
o ou t
AA er rS o
ll lI ll(ll jljl.l jfljl ! I' l l l 1lllll ti
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (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 oftheplantfortransientsandaccidents.
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 - Nuclear Training l and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Quality Control and Support and shall meet l or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) ,
i
'~
i FUNCTION 6.5.1.1 The POSRC shcIl function to advise the Manager-Nuclear Operations on l i
all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The POSRC shall be composed of the:
Chairman: Manager-Nuclear Operations i Member: General Supervisor - Operations i
, Member: General Supervisor - Electrical and Controls Member: General Supervisor - Chemistry Member: General Supervisor - Mechanical Maintenance Member: General Supervisor - Technical Services Engineering Member: , General Supervisor - Radiation Safety l
Member:
Memue General Supervisor - Plant and Project Engineering l Genera' 5.ver r iser - ocsip Engine.wl"f l
ALTERfd () Genei4 A f W U'" ' 0"*ht7 th5%"*" C f.5.1.3 All dternate. members shall be appointed in writing by the POSRC i
Chairman to senc ca a temoocary basis; howeve,, no more than two alternates j shall per*.icipate as voting umbers in POSRC activities at any one time.
C ALVERT' CLIFFS - UNIT 2 6-6 Amendment No. JJ J5,36,ff,EB, 93 l
'..% J.- .x
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chairman or his designated alternate and 4eur-members including alternates.
five RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:
- a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Manager-Nuclear Operations to affect nuclear safety. l
- b. Review of all proposed tests and experiments that affect nuclear safety,
- c. Review of all proposed changes to Appendix "A" Technical Specifications,
- d. Review of all proposed changes or modifications to plant systems or -
equipment that affect nuclear safety,
- e. Investigation of all violations of the Technical Specifications includ-
- ing the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President-Nuclear Energy and to the Chairman of the Off Site Safety Review Comittee.
, f. Review of all REPORTABLE EVENTS. .
- g. Review of facility operations to detect potential safety hazards.
- h. Performance of special reviews, investigatinns or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review
/ Comittee. '
- i. Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee.
- j. Review of the Emergency Plan and implementing procedures and shall submit reconcended changes to the Off Site Safety Review Comittee.
- k. Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recomendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Manager-Nuclear Operations and the Off Site Sciety Review Comittee. ,
- 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
CALVERT CLIFFS - UNIT 2 6-7 Amendment No. 17,75,26,75, N6,93 m .