Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305ML20204J158 |
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Millstone  |
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Issue date: |
03/19/1999 |
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From: |
NORTHEAST NUCLEAR ENERGY CO. |
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Shared Package |
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ML20204J154 |
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References |
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NUDOCS 9903300015 |
Download: ML20204J158 (9) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F ML20154C0491998-09-28028 September 1998 Proposed Tech Specs Revising FSAR Separation Requirement of Six Inches Which Is Applied to Redundant Vital Cables, Internal Wiring of Redundant Vital Circuits & Associated Devices ML20154A3701998-09-28028 September 1998 Proposed Tech Specs Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1, 3.6.5.1,3.7.6.1 & 3.9.15,revising Info Re Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA ML20151V5011998-09-0909 September 1998 Proposed Tech Spec Changing TS Definitions 1.24,1.27,1.31, 3.0.2,4.0.5,3.2.3,3.3.2.1,3.4.1.1,3.4.11 & Adding TS 3.0.6 B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified1998-08-12012 August 1998 Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified B17341, Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval1998-08-0606 August 1998 Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval ML20236Y0831998-08-0404 August 1998 Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves ML20236X2521998-07-30030 July 1998 Proposed Tech Specs Bases 3/4.9.1,3/4.1.1.3,3/4.7.1.6, 3/4.7.7,3/4.5.4 & 3/4.3.3.10,resolving Miscellaneous Condition Repts ML20236W0201998-07-30030 July 1998 Proposed Tech Specs Bases Section 3/4.6.1.1,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236T2681998-07-21021 July 1998 Proposed Tech Specs Re Reactor Protection & ESFs Trip Setpoints ML20236T5301998-07-17017 July 1998 Proposed Tech Specs Pages for TS Bases Section 3/4.4.9, Pressure/Temperature Limits ML20236T7331998-07-17017 July 1998 Proposed Tech Specs Modifying DG Testing Requirements ML20249A2811998-06-10010 June 1998 Proposed Tech Specs Re Post Accident Access to Vital Areas (Plar 3-98-6) ML20249A3121998-06-0606 June 1998 Proposed Tech Specs Re SLCRS Bypass Leakage (Plar 3-98-5) ML20249A2681998-06-0505 June 1998 Proposed Tech Specs Re Revised Steam Generator Tube Rupture Analysis (Plar 3-98-4) ML20248M2221998-06-0404 June 1998 Revised Tech Specs Pages,Changing TS Bases Section 3/4.7.1.5 to Reword Section Which Describes Limiting Temperature Case for Containment Analysis ML20247G6841998-05-14014 May 1998 Proposed Tech Specs,Modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage1998-05-0707 May 1998 Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247B9411998-05-0101 May 1998 TS Change Pages for TS Bases Section 3/4.5.4,modifying Wording Associated W/Refueling Water Storage Tank Minimum Boron Concentration ML20217D5941998-04-30030 April 1998 Proposed Tech Specs Re Change to Basis 3/4.6.4 Which Modifies Accuracy Range Associated W/Measured Std Cubic Feet Per Minute & Corrects Listed Component Number 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program 1999-09-07
[Table view] |
Text
_ _.. -
Docket No. 50-245 B17702 Millstone Nuclear Power Station, Unit No.1 3
Marked Up Pages March 1999
~~
9903300015 990319 PDR ADOCK 05000245; P
PM_
_. j
I
' ADMINISTRATIVE CONTKOLS i
6.1 NESPONSIBILITY S.1.1 TS: Str.i;r Vic: "raident =d Chki ".=10:r Offlect (CT)
Milht"00
- hell t; re;p;a;ibl; f;r ever;1 ;p;retisa ef the Millst;as St;ti= Sit; ;^hW
@Suf thi Mill 3tene 'Jait "ecewry Offi.cer shell 1,e resp;;sible f:r ';;rell ;.it l A
=f cperetica and the Direct;r, Unit Operetiens shell be respeasibk f*
Oper:tien of the =it. n : :=i r Vice Prc:idst =d CT Mil ktent.
"ill;t:n; "ait i "ac;;;ry Offic;r, =d Oirst:r del:5^.te, i. i;ritias, th; n;;;nier te th;n ra, 5 t ";;r;ti:= :h:W-ew,h abtence.
p=:ibilitie: d:rin" th0i+-
6.1.2 The shift Manager on site shall be responsible for the conmand
- 2,a function.
8
~**
SJ ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate managemant, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be a.
established and defined for the higher management levels through intermediate levels to and including all operating organization position:,.
These relationships shall be documented ard updated, as appropriate, in the form of organization charts ~, functional descrip-tions of departmental re'sponsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirernents shall be documented in the Quality Assurance Topical Report.
b.
The Ml hter
.M NE'c'Iry Officer shall be re asible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
on.
The Senier V k: p ta o %
c.
,raidat ar,d CM0
" ilk,tw shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to ensure nuclear safety, d.
The individuals who train the Certified Fuel Handlers and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have suffi-cient organirational freedom to ensure their ability to perform their assigned functions.
l G.2.2 FACILITY STAFF Each on duty shift shall be composed of at least the minimum shift a.
crew composition shown in Table 6.2-1.
j i
b.
At least one person qualified to stand watch in the control room shall be present in the control room when irradiated fuel is stored in the fuel pool.
Hillstone Unit 1 6-1 Amendment No. 72, 55. 79 97 104 0322 1
I
'4 4
insert A 6.1.1 The Designated Officer shall be responsible for overall operat;on of the Millstone Station site and shall delegate in writing the succession to this responsibility. The Designated Manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession to this responsibility.
Insert B 6.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles.
Unit specific titles for the functions and responsioilities associated with these generic titles are identified in the Quality Assurance Topical Report.
i
?
1 ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 An NRC approved training and retraining program for the Certified Fuel Handlers shall be maintained.
6.5 REVIEW AND AUDIT
)
6.5.1 Plant 00erations Review Committee (PORC)
.Eustina j
bes:
6.5.1.1
..I r1. 5e,.
The PORC shall function to advise the -Direct;r,g"r.it Opre.ier.s on
\\
all matters related to nuclear safety.
C_ojnposition 6.5.1.2 The PORC shall be composed of nine to eleven members.
Members shall collectively have experience and expertise in the following areas:
Plant Operations
{
Engineering Reactor Engineering Maintenance Instrumentation and Controls Health Physics Chemistry Work Planning Quality A**urance The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years
)
technical experience in their respective field of expertise.
i The members of PORC shall be appointed in writing by the Mrect r, " nit n y.,.
s,.:f. o.r j
0 craticas.
The Chairperson and alternate Chairperson of the PORC
)
sball be drawn from the PORC members and be appointed in writing b i
the Circctor, l'ait Oprations.
b% ~~ + *.!
n~~ y e 6.5.1 3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit 1 6-5 Amendment No. 77, 75, 7J p), pp, 104
ADMINISTRATIVE CONTROLS 1
i Quality Control for effluent monitoring using the guidance in 9
Regulatory Guide 1.21 Rev.1, June 1974.
h.
Radiological Effluent Monitoring and offsite Dose calculation Manual (REM 00CM Environme)ntal Monitoring. implementation, except for Section I.E., Radiolog The0Y$It'$f,$W5rb.Y3f.f:#$NEtf:: SYiPION:[0'f'ficer, 6.8.2 a.
0 r
cr Ernier V!: Prc:ident : d C"O "ilht-- may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. The review per the Qualified Reviewer Program shall be it, accordance with Speci.f* ition 6.5.4.
b.
Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be a'pproved by the Dir;;t:r, "-it Oper:tt::: er S:nier ou:y.a.a Vk Prc:id:nt :nd C"O "ilutet: or by cognizant Manager or u,,, fDirectors who are designated as the Approval Authority by the p
o..:3 +.4 3 ' Direct:r, Unit Operat4:n: ;r 5:ni:r Yi;; 77;;id:nt and C"O iithun; as specified in administrative proceduras. The Approval Authority for each procedure and program or class of procedure and 3
program shall be specified in administrative procedures.
)
Each procedure of Specification 6.8.1, and changes thereto, shall be c.
i reviewed by the PORC or SORC and shall be aproved by the Dir::t:r, D";34*J Wit Sp:r: tier,: cr Senier Y k: Prc:id:;t
,_ C"O "il htene, or be
%~-
" +3 reviewed and approved in accordance with the Station Qualified
- ++d Reviewer Program, prior to implementation. Each procedure of 4
i Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
The intent of original procedure is not altered.
a.
b.
The change is approved by two members of the plant management staff, at least one of whom is a certified Fuel Handler.
l The change is documented, reviewed b c.
Station Qualified Reviewer Program, y the PORC or SORC, or the as applicable, and approved by D'5:r + 4 the circ ttr Unit Oper:ti:n:, :r th: u n Sr Vie: Prt:ident :nd CNC D.'gr;y "ilhtent o. Station Qualified Reviewer Program Department Manager within 14 days of implementation.
. m.,,
6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.
Millstone Unit 1 6-15 Amendment No. M.
U, 9/, PP,104 0323
Docket No. 50-245 B17702 Millstone Nuclear Power Station, Unit No.1 Retyped Pages March 1999
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Designated Officer shall be responsible for overall operation of the Millstone Station Site and shall delegate in writing the succession to this responsibility.
The Designated Manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession to this responsibility.
4 6.1.2 The Shift Manager shall be responsible for the control room command function.
6.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles.
Unit specific titler, for the functions and
)
responsibilities associated with these generic titles are' identified in tb Quality Assurance Topical Report.
l 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate manag ment, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
1 a.
Lines of authority, responsibility, and communication shall be established and defined for the higher management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
b.
The Designated Manager shall be responsible for overall unit safe l
operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Designated Officer shall have corporate responsibility for I
overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the Certified Fuel Handlers and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have suffi-cient organizational freedom to ensure their ability to perform their assigned functions.
6.2.2 FACILITY STAFF a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one person qualified to stand watch in the control roo9 shall be present in the control room when irradiated fuel is stored in the fuel pool.
Millstone Unit 1 6-1 Amendment No. p. M. N, M, ##,
t-
[-
)
1 l.
J l
l l
ADMINISTRA TIVE CONTROLS 6.4 TRAINING-l 6.4.1 An NRC approved training and retraining program for the Certified l
Fuel Handlers shall be maintained.
6.5 REVIEW AND AUDIT 6.5.1 Plant Operations Review Committee (PORC)
Function 6.5.1.1 The PORC shall function to advise the Designated Manager on all I
q matters related to nuclear safety.
Composition i
6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:
l Plant Operations Engineering Reactor Engineering l
l Maintenance Instrumentation and Controls l
Health Physics Chemistry Work Planning Quality Assurance l
The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years i
technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the Designated Manager. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Designated Manager.
I i
Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC l
Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit 6-5 Amendment No. pp, JJ 7J. 77, 77
- Jpp, 0328-b_
m A
AMINISTRATIVE CONTROLS l
g.
Quality Control for effluent monitoring using the guidance in Regulatary Guide 1.21 Rev. 1, June 1974.
i h.
Radiological Effluent Monitoring and Offsite Dose Calculation Manual l
(REMODCM) implementation, except for Section I.E., Radiological i
Environmental Monitoring.
6.8.2 a.
The Designated Manager, Designated Officer or Designated Senior i
l Officer may designate specific procedures and programs, or classes of l
procedures and programs to be reviewed in accordance with the Station l
Qualified Reviewer Program in lieu of review by the PORC or SORC.
The review per the Qualified Reviewer Program shall be in accordance with Specification 6.5.4.
l b.
Procedures and programs listed in Specification 6.8.1, and changes i
thereto, shall be approved by the Designated Manager or Designated l
Officer or by cognizant Manager or Directors who are designated as the Approval Authority by the Designated Manager or Designated l
Officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and l
program shall be specified in administrative procedures.
c.
Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the PORC or SORC and shall be approved by the Designated Manager or Designated Officer, or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to 4
implementation.
Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of original procedure is not altered.
b.
The change is approved by two members of the plant management staff, l
at least one of whom is a Certified Fuel Handler.
c.
The change is documented, reviewed by the PORC or S0RC, or the Station Qualified Reviewer Program, as applicable, and approved by the Designated Manager or Designated Officer or Station Qualified l
Reviewer Program Department Manager within 14 days of implementation.
i 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 0DCM.
l l
}
Millstone Unit 1 6-15 Amendment No. 5, 7J U, #, J#,
0329