Proposed Tech Spec Pages 212,213 & 214 Re Administrative ControlsML20106H480 |
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Site: |
Pilgrim |
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Issue date: |
02/08/1985 |
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From: |
BOSTON EDISON CO. |
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To: |
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Shared Package |
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ML20106H471 |
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References |
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NUDOCS 8502150319 |
Download: ML20106H480 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20072T0521994-09-0606 September 1994 Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe ML20072S0501994-09-0606 September 1994 Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems ML20072S0081994-09-0606 September 1994 Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief ML20072S0861994-09-0606 September 1994 Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20069M3311994-06-0909 June 1994 Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe ML20067B7111994-02-0909 February 1994 Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993 Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059A9361993-10-19019 October 1993 Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993 Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint ML20046D0441993-08-0909 August 1993 Proposed Tech Specs,Proposing 24 Month Fuel Cycle ML20044G1331993-05-20020 May 1993 Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993 Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively 1999-06-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] |
Text
[ .- .
Attachment A (Revision 1)
Proposed Technical Specification Changes NOTE: Because of a prior license amendment request involving the deletion of Licensee Event Report requirements (Ref. Gen. Ltr.
83-43 12/19/83),- it will be noted, when reviewing the following submittal, that certain paragraphs of Section 6 incorporate the previously requested changes. This was done at the request of the NRC's P'igrim Station Project Manager, Mr. Paul Leech and to simplify the review of this submittal.
Proposed Change:
Reference is made to Pilgrim Nuclear Power Station, Technical Specifications
- Sections 6.1 thru 6.8 and, Figures 6.2.1 and 6.2.2. The following changes are requested to be made:
- 1) Section-6.1, pg. 208 Change: "The Station Manager shall be accountable for overall facility operation. In his absence the Station-Manager shall designate in writing the individual to assume this responsibility."
To: "The Nuclear Operations Manager shall be accountable for overall
' facility operation. .In.his absence the Nuclear Operations Manager shall designate in writing the individual _to assume this responsibility".
- 2) Section 6.5.A.1, pg. 212 Change: The ORC shall function to advise the' Station Manager on~all matters related to safety".
To: "The ORC shall function to advise the Nuclear Operations Manager on all matters related-to safety.
- 3) Section 6.5.A.2, pg. 212 Change the entire Section 2. entitled " Composition".
Change: 2. COMPOSITION
'The ORC shall b'e composed of the Chai.rman: Station Manager _ _
Member: Chief Operating. Engineer Member: -Chief Technical Engineer Member: ' Chief Maintenance Engineer Member: Chief Radiological Engineer s
. Member: Onsite: Safety & Performance Group Leader n The-ORC Chairman may appoint subcommittees _ composed of
~ personnel who are not members of ORC to_ perform staff work
[ '
necessary to the efficient functioning of ORC.
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, ss . 8502150319 850208 PDR ADOCK 05000293 P PDR ,
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. To: 2. COMP'OSITION
' ~
The ORC shall be composed of the:
Chairman: Technical Section Head Members: Chief Operating Engineer Chief Maintenance Engineer u Chief Technical Engineer Chief Radiological Engineer Chief Chemical Engineer.
Onsite Safety and Performance Group Leader
- 4) .Section
- 6.5.A.3, pg. 212 LChange: " Alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis;'however, no more than two alternates shall participate in an ORC quorum at any one time".
To: ." Alternates shall be appointed in writing by the Nuclear Operations Manager to serve on a temporary basis".
.5) -Section 6.5.A.5, pg. 212 Change: "A quorum of the ORC shall consist of the Chairman and a majority of. members including alternates".
To: -" A quorum o'f the ORC shall consist'of,the Chairman or designated.
-alternate;and a majority of members / designated' alternates;.
however, no more than two alternates shall.be allowed lto meet-quorum requirements". <
~
- 6) Section 6.5.A.6, pg. 212 Change: "e. ' Investigation of all violations of the Technical Spec-
-ifications................to the Vice President -
. Nuclear. Operations and to the .NSRAC Chairman".
To: "j. Inve'stigation of all violations of the Technical:
. Specifications.and shalll prepare and forward.a reportL ;j covering evaluation and recommendations to prevent' -
- recurrence-to the Nuclear Operations _ Manager, the-NSRAC. Chairman,.and the Vice-President - Nuclear Operations.
% Delete: "h. ~ Review.the Station Fire. Protection Plan _;..etc." ,
1 Renumber: .Section 6.5.A.6 parts "k" and "1"
~
, To: Section 6.5. A;7 parts 1'b" and "c" respectively.
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__,______.,_,-__L__-________,
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w .-
._ Note: A re-arrangement of the list of responsibilities will be necessary due to the above changes.
~ Add-as a new' paragraph:
The ORC Chairman may appoilt-subcommittees composed of personnel who are not members of ORr, to perform staff work necessary to the efficient functioning of ORC.
- 7) Section 6.5.A.7, pg. 213 Change: '! 7 . Authority
- The ORC shall report to and advise the Station Manager on those areas of responsibility specified in Section
'T 6.5.A.6."
To: "7. Authority
- a. Recommend in writinc to the Nuclear Operations Manager approval or disapproval of items considered under 6.5.A.6(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.A.6(a) through (d) above constitutes an unreviewed safety question.
- c. Provide -immediate wr1tten notification to -the Nuclear Operations Manager,_the Nuclear-Safety Review and.
Audit Committee and the Vice President - Nuclear-
. Operations, of disagreement between the ORC Members and the ORC Chairman. The Nuclear Operations Manager shall have responsibility for resolution for such:
disaareement.
- 8) 1Section 6.5.A.8, pg._213 y Change: "8. -RECORDS
'The' ORC.shall maintain written ~ minutes of each meeting.
and'_ copies shallEbe provided to the Vice.PresidentE E Nuclear Operations."
To: "8. RECORDS
!The'0RC shall. maintain written Minutes _of:each meeting
[<' and copies shall be forwarded to the NuclearL0perations til Manager Nuclear _. Safety Review ~and_ Audit: Committee e Chairman,--and the Vice President - Nuclear Operations.
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Attachment B (Revision 1) 6.5 REVIEW AND AUDIT A. OPERATIONS REVIEW COMMITTEE (ORC)
- 1. FUNCTION The ORC shall function to advise the Nuclear Operations Manager on all matters related to safety.
- 2. COMPOSITION The ORC shall be composed of the:
Chairman: Technical Section Head Members: Chief Operating Engineer Chief Maintenance Engineer =
Chief Technical Engineer Chief Radiological Engineer Chief Cnemical Engineer Onsite, Safety and Performance Group Leader-
- 3. ALTERNATES Alternates shall be appointed in writi- by the Nuclear Operations Manager to serve on a temporary basis . wever, no more than two alternates shall participate as vt ng members in (ORC) at any one time.
- 4. MEETING FREQUENCY The ORC shall meet at least once per calendar month and as
. convened by the ORC Chairman.
- 5. QUORUM The minimum quorum of the (ORC) necessary for the performance of the (ORC) responsibility and authority provisions of'these Technical Specifications shall consist of the Chairman or his designated alternate and.four members including alternates.
- 6. RESPONSIBILITIES The ORC 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 that affect nuclear safety.
Amendment No. 212
.. _ .. . . . . . . . . . _. _ .. _..- .. . .. . .. .. . . ,, . . . . . _ ~ . ..
m
- 6. RESPONSIBILITIES (Cont.) -
- b. Review all proposed tests and experiments that affect -
nuclear safety. .
l
- c. Review of all proposed changes to the Technical '
Specifications. -
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Review of facility operations to detect potential safety hazards. -
- f. Review of the Station Security Plan and implementing -
h procedures and changes to the plan and procedures. =
- g. Review of the Emergency Plan and implementing procedures and changes to the plan and procedures. *F
=:
- h. Performance of special reviews and investigations and reports thereon as requested by the NSRAC Chairman. ,. =
i Investigation of all violations of the Technical Specifica-tions and shall prepare and forward a report covering ~.
evaluation and recommendations to prevent recurrence to the Nuclear Operations Manager, the NSRAC Chairman, and the Vice President - Nuclear Operations.
The ORC Chairman may appoint subcommittees composed of personnel ,' .
who are not members of ORC to perform staff work necessary to :
the efficient functioning of ORC. #
l
- 7. AUTHORITY l
~~ ~
- a. Recommend in writing to the Nuclear Operations Manager .
approval or disapproval of items considered under 6.5.A.6(a) through (d) above. -
}
- b. Render determinations in writing with regard to whether or "
2 nat each item considered under 6.5.A.6(a) through (d) above constitutes an unreviewed safety question.
- c. Provide immediate written notification to the Nuclear Opera- .
tions Manager, the Nuclear Safety Review and Audit Committee ?
and the Vice President - Nuclear Operations, of disagreement between the ORC Members and the ORC Chairm 1. The Nuclear . 2 Ooerations Manager shall have responsibility for resolution ~
for such disagreements. -
- 8. RECORDS ,
i The ORC shall maintain written Minutes of each meeting and copies shall be forwarded to the Nuclear Operations Manager, the Nuclear Safety Review and Audit Committee Chairman, and the
=
i Vice President - Nuclear Operations.
- c Amendment No. 213
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B. NUCLEAR SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC)
- 1. FUNCTION The NSRAC'shall function to provide independent review and audit of designated activities in the areas of:
.: s
. nuclear power plant operations; 1.
- 2. nuclear engineering;
. 3. chemistry and radiochemistry;
- 4. metal,lurgy; -
- 5. Instrumentation and co.itrol;
- 6. radiological safety;
'?
- 7. mechanical-and electrical engineering;
- 8. quality assurance practices
- 9. fire protection 2 .- COMPOSITION The NSRAC Chairman and other members shall be appointed by the Senior Vice President - Nuclear, or such other person as he shall designate. NSRAC members shall collectively possess experience and competence required to review and audit the designated areas noted in.
6.5.B.1.
~
' r.
The collective competence of the committee will be maintained as changes to the membership are made. The membership shall consist of a minimum of five-persons.
- 3. ALTERNATES Alternate members shall be. appointed in wrlting bylthe Senior Vice-
- President - Nuclear or. the chairman to serve on a temporary basis;
, - ; :however,.no more than two alternates shall. participate in a quorum.at -
~any 'one time.
. '4. -CONSULTANTS.
.Consultantsshallbeutilizedas'determinedbythe-NSRAC;Ch$1rmanto provide expert advice.to the-NSRAC.
5; MEETING FREQUENCY The:NSRAC shall. meet at least once per six. months.
y
- 6. QUORUM A quorum.of.the?NSRAC shall consist of the Cfiatrman'and a majority of; the'.NSRAC memberstincltiding alternates. _ No more than a minority of.
ithe; quorum shall:have line. responsibility for.' operation of the
~
. facility. -
s 4 j N
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a .214 (AmendmentiNo. N- -
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