|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop ML20036A1891993-04-30030 April 1993 Proposed TS 3/4.8, Electrical Power Sys, Paragraph 4.8.1.1.2.b,that Deals W/Automatic Load Sequence Timers on EDGs to Be Implemented During Upcoming Cycle 17 Refueling Outage ML20035G8601993-04-23023 April 1993 Proposed TS Shutdown Margin Requirements for Change in Cladding from Stainless Steel Clad Core to Zircaloy Cladding for Cycle 18 Operation ML20035A7561993-03-22022 March 1993 Proposed Tech Specs Addressing Special Test Exceptions, Electrical Power Sys Shutdown Relief Valves & Service Water Sys ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup B14391, Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing1993-03-16016 March 1993 Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria B13751, Proposed Tech Specs Re Steam Generator Overfill Protection1991-02-28028 February 1991 Proposed Tech Specs Re Steam Generator Overfill Protection ML20029B0671991-02-28028 February 1991 Proposed Tech Specs Adding Footnote to Tech Spec Table 4.3.1 Item 16, Reactor Trip Sys Breakers ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases B13555, Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-06-25025 June 1990 Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation ML20043G6311990-06-14014 June 1990 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements ML20043H0231990-06-0808 June 1990 Proposed Tech Specs Re Reactor Trip Sys Instrumentation Response Times B13520, Proposed Tech Specs Supporting Cycle 16 Operation1990-05-0909 May 1990 Proposed Tech Specs Supporting Cycle 16 Operation B13503, Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys1990-04-24024 April 1990 Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys ML20033F5551990-03-14014 March 1990 Proposed Tech Specs,Allowing Testing of Individual Rod Position Indication Sys During Power Operation B13450, Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields1990-02-16016 February 1990 Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields ML19332E4381989-11-22022 November 1989 Proposed Tech Specs Re Reactor Trip Sys Trip Setpoints & ESFAS Instrumentation B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal1989-09-29029 September 1989 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal 1999-08-24
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20046C1421993-07-0909 July 1993 Rev 12 to Response to Loss of Secondary Heat Sink ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20045H2271993-05-18018 May 1993 Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection ML20045G7991993-05-0707 May 1993 Rev 1 to Project Plan,Cyap Seismic Upgrade Program for Svc Water Sys,Feedwater Sys & Main Steam Sys Outside Containment B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop 1999-08-24
[Table view] |
Text
"
l m
3 gg
. ADMINISTRATIVE CONTROLS l
l b.
The NSAB shall have experience in and shall function to provide independent oversight review and audi4 of designated activities in the areas of:
1.
Nuclear power plant operations; l
2.
Nuclear engineering; 3.
Chemistry and radiochemistry; 4.
Metallurgy; 5.
Instrumentation and control; 6.
Radiological safety; 7.
Mechanical and electrical engineering; and 8.
Quality assurance practices.
The NSAB serves to advise the re:ident :nd Chief Ex::utiv: Of'!:er on matters related to nuclear safety and nottry the*re:ident :nd Chi:f Extentiv Offf:cr within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement between the NSAB and the organization or function being reviewed.
COMPOSITION 6.5.2.2 The rc:ident :.nd Chief Ex:: tiv: Offi: r shall appoint, in writing, l a minimum of seven members to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide 1'ndependent review and audit in the areas listed in j
Specification 6.5.2.1.
ALTERNATES 6.5.2.3 All alternate members shall be appointed, in writing, by the Prc:ident and CM ef Executhe Of-f4m; however, no more than two alternates shall participate as members in NSAB activities at any one time.
MEETING FRE0VENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.
000 RUM 6.5.2.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit.
No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
,, zw.
=
Executive Vice President and Chief Nuclear Officer HADDAN NECK 6-8 Amendment No. JJJ JJJ, JFF, JFJ, 9702120239 970131 PDR ADOCK 05000213 P
PDR x
. ADMINISTRATIVE CONTROLS REVIEW RESPONSIBILITIES 6.5.2.6 The NSAB shall be responsible for the review of:
a.
The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59; b.
Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59; c.
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59; d.
Proposed changes to Technical Specifications and the Operating License; e.
Violations of applicable codes, regu btlons,, orders, license requirements, or internal procedures naving nuclear safety significance; l
f.
All Licensee Event Reports required by 10 CFR 50.73; g.
Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; j
h.
Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence; i
1.
Significant operating abnormalities or deviations from ncrmal and expected performance of equipment that could affect nuclear safety; j.
The performance of the corrective action program; and k.
Audits and audit plans.
Reports or records of these reviews shall be forwarded to the Fr+ sider.t nr.d GMef Executive Officee within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES i
6.5.2.7 The NSAB audit program shall be the responsibility of Nuclear Oversight organization.
NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
The conformance of unit operation to provisions contained within the a.
Technical Specifications and applicable license conditions; 1
]
Executive Vice PresiderL and Chief Nuclear Officer l
HADDAM NECK 6-9 Amendment No. JgJ. JJJ, JJJ.
0411
~
. ADMINISTRATIVE CONTROLS i
i w=
Executive Vice President and Chief Nuclear Officer b.
The training and qualifications of the unit staff; l
c.
The implementation of all programs required by Specification 6.8; d.
The Fire Protection Program and implementing procedures; e.
The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
f.
Actions taken to correct deficiencies occurring in equipment, j
structures, systems, components, or method of operation that affect nuclear safety; and g.
Other activities and documents as requested by the Prc:id=t =d Chief Executive Of#icer.
9
)
RECORDS 6.5.2.8 Written records of reviews and audits shall be maintained.
As a minimum these records shall include:
1 a.
Results of the activities conducted under the provisions of Section 6.5.2; b.
Recommended approval or disapproval of items considered under Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and c.
Determination as to whether each item considered under Specification 6.5.1.6.a, 6.5.1.6.b, 6.5.1.6.d and 6.8 constitute an s
unreviewed safety question as defined in 10 CFR 50.59.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Comission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of the NSAB and the Executive Vice President and Chief Nuclear Officer.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
HADDAM NECK 6-10 Amendment No. JgJ JJJ JJJ.
0411
. -..~.-
o l
Docket No. 50-213 B16167 i
)
f I
i i
i l
Haddam Neck Plant i
i Addendum To The Proposed Revision To Technical Specifications Administrative Controls I
l Retyped Pages l
1 r
l l
t i
i l
l l
4 January 31,1997
ADNINISTRATIVE CONTROLS b.
The NSAB shall have experience in and shall function to provide 4
independent oversight review and audit of designated activities in the areas of:
1.
Nuclear power plant operations; 2.
Nuclear engineering; 3.
Chemistry and radiochemistry; 4.
Metallurgy; 5.
Instrumentation and control; 6.
Radiological safety; 7.
Mechanical and electrical engineering; and 8.
Quality assurance practices.
The NSAB serves to advise the Executive Vice President and Chief Nuclear Officer on matters related to nuclear safety and notify the Executive Vice President and Chief Nuclear Officer within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement j between the NSAB and the organization or function being reviewed.
j l
COMPOSITION 6.5.2.2 The Executive Vice President and Chief Nuclear Officer shall appoint, l in writing, a minimum of seven members to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson.
The membership shall function to provide independent review and audit in the areas listed in 4
Specification 6.5.2.1.
ALTERNATES 6.5.2.3 All alternate members shall be appointed, in writing, by the Executive Vice President and Chief Nuclear Officer; however, no more than two alternates shall participate as members in NSAB activities at any one time.
1 MEETING FREQUENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.
000 RUM 6.5.2.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit.
No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirem; cts.
4 HADDAN NECK 6-8 Amendment No. JJJ, JJJ, JJJ, JJJ, 0411
u 1
9 ADMINISTRATIVE CONTROLS REVIEW RESPONSIBILITIES 6.5.2.6 The NSA8 shall be responsible for the review of:
a.
The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59; b.
Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59; c.
Proposed tests or experiments that involve an unreviewed safety l
question as defined in 10 CFR 50.59; i
d.
Proposed changes to Technical Specifications and the Operating License; e.
Violations of applicable codes, regulations,
- orders, license requirements, or internal procedures having nuclear safety significance-f.
All Licensee Event Reports required by 10 CFR 50.73; g.
Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; h.
Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence; i.
Significant operating abnormalities or deviations from normal and expected performance of equipment that could affect nuclear safety; j.
The performance of the corrective action program; and k.
Audits and audit plans.
Reports or records of these reviews shall be forwarded to the Executive Vice President and Chief Nuclear Officer within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES 6.5.2.7 The NSAB audit program shall be the responsibility of Nuclear Oversight organization.
NSA8 audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; HADDAM NECK 6-9 Amendment No. JJ), 157, JJJ.
0411
ADMINISTRATIVE CONTROLS 8
j b.
The training and qualifications of the unit staff; c.
The implementation of all programs required by Specification 6.8; d.
The Fire Protection Program and implementing procedures; e.
The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an j
outside independent fire protection consultant.
f.
Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect j
nuclear safety; and l
g.
Other activities and documents as requested by the Executive Vice President and Chief Nuclear Officer.
4 RECORDS i
6.5.2.8 Written records of reviews and audits shall be maintained.
As a i
minimum these records shall include:
a.
Results of the activities conducted under the provisions of Section 6.5.2; b.
Recommended approval or disapproval of items considered under Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and c.
Determination as to whether each item considered under Specification 6.5.1.6.a. 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an i
unreviewed safety question as defined in 10 CFR 50.59.
l 6.6 REPORTABLE EVENT ACTION l
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
i I
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of the NSAB and the Executive Vice President and Chief Nuclear Officer.
l t
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
HADDAN NECK 6-10 Amendment No. JJJ, JJJ, JJJ, 0411