Proposed Changes to Section 6 Tech Specs Re Onsite Safety Committee & Offsite Review Committee Membership & ResponsibilitiesML20067D447 |
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Beaver Valley |
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12/06/1982 |
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DUQUESNE LIGHT CO. |
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Shared Package |
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ML20067D399 |
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NUDOCS 8212130264 |
Download: ML20067D447 (8) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20199J4391998-01-29029 January 1998 Proposed Tech Specs Re Radiological Doses for Locked Rotor Accident ML20198D4081997-12-19019 December 1997 Proposed Tech Specs,Modifying Neutron Flux Requirements to Allow Use of Alternate Detectors ML20198P6571997-11-0404 November 1997 Proposed Tech Specs Table 3.3-4 Re Emergency Bus Undervoltage Trip Setpoint,Allowable Valve & Time Delay for DG Start ML20212C8881997-10-22022 October 1997 Proposed Tech Specs 3.4.8,reducing RCS Specific Activity Limits Per GL 95-05 ML20217A9801997-09-11011 September 1997 Proposed Tech Specs Implementing line-item Improvements Provided in GL 93-08 for Removal of Response Times from TS ML20210L4381997-08-13013 August 1997 Proposed Tech Specs Revised Typed Pages for TS Change Requests 213 & 80,requiring Addl Revs from Pages Submitted in ML20141K5371997-05-23023 May 1997 Proposed Tech Specs Re Typed Paged for Change Request 213 & 80 ML20137C9111997-03-14014 March 1997 Proposed Tech Specs Re Administrative Controls Related to QA ML20147E6511997-03-10010 March 1997 Proposed Tech Specs Modifying Specification 3.4.5 to Allow SG Tube Sleeving Using Framatome Process ML20136G2091997-03-10010 March 1997 Proposed Tech Specs,Modifying Spec 3.4.5 to Allow SG Tube Sleeving Using CE Process ML20147E6301997-03-10010 March 1997 Proposed Tech Specs Modifying Unit 1 Design Feature Section 5.2.1 to Add ZIRLO as Fuel Assembly Matls & Adds Ref to NRC Approved WCAP-12610 to Administrative Control 6.9.1.12 for Both Units 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20205F6961998-11-30030 November 1998 Revs to Offsite Dose Calculation Manual ML20211K6871998-11-30030 November 1998 Issue 2,Rev 1 to Inservice Testing (IST) Program for Pumps & Valves ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20154D5241998-08-14014 August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements 1999-09-22
[Table view] |
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ATTACilMENT A
- 1. Remove pages 6-5, 6-7, 6-8, 6-10, 6-11
- 2. Insert pages 6-5, 6-7, 6-8, 6-10, 6-11 l
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS -
6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiological Operations Coordinator who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shif t 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 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 Director Nuclear Division Training 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.
6.4.2 A Training program for the Emergency Squad shall be maintained under the direction of the Director Nuclear Division Training and shall meet or exceed the requirements of Section 27 of the NEPA Code-1976.
6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)
FUNCTION '
6.5.1.1 The OSC shall function to advise the Station Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The OSC shall be composed of the: _
Chairman: Chief Engineer Member: Senior Licensed Operator Member: Radiation Control Foreman Member: Maintenance Engineer Member: Senior Engineer - Station Engineering Member: Senior Testing or Study Projects Coordinator Member: Shif t Technical Advisor Member: Chemist Member: Quality Control Engineer l,l NOTE: The chairman of the OSC shall appoint an individual from each of the above listed job categories to serve as a member of the OSC for a period of at least 6 months.
NOTE: OSC members shall meet or exceed the minimum qualifications of ANSI i N18.1-1971 Section 4.4 for comparable positions. The SRO shall meet I the qualifications of Section 4.2.2 and the Maintenance Engineer will Meet the qualifications of Section 4.2.3. l l
BEAVER VALLEY - UNIT 1 6-5 PROPOSED WORDING
r ADMINISTRATIVE CONTROLS AUTHORITY 6.5.L.7 The OSC Shall:
- a. Recommend to the Plant Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
- c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Operations and the Of f site Review Committee of disagreement between the OSC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such dfsagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The OSC shall maintain written minutes of each meeting and copies shall be provided to the Manager of Nuclear Operations and Chairman of the Offsite Review Committee.
6.5.2 0FFSITE REVIEW COMMITTEE (ORC)
FUNCTION i
6.5.2.1 The ORC shall function to provide independent review and audit of designated activities in the areas of:
- a. nuclear power plant operations t
- b. nuclear engineering BEAVER VALLEY - UNIT L 6-7 PROPOSED WORDING l
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ADMINISTRATIVE CONTROLS
- c. chemistry and radiochemistry
- d. metallurgy 4
- e. instrumentation and control
- 1. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices COMPOSITION 6.5.2.2 The' ORC shall be composed of the:
Chairman: Vice President, Nuclear Division Vice Chairman: Manager, Nuclear Safety and Licensing Member: Manager, Nuclecr Engineering Membe r: Manager, Nuclear Operations Member: Manager, Regulatory Affairs, Beaver Valley Power Station Unit No. 2 Member: Senior Project Engineer, Nuclear Engineering Department Member: Manager, Nuclear Support Services Member Site Service Manager, Westinghouse Electric Corporation Member: Manager, Quality Assurance Member: Director, Environmental and Radiological Safety Programs
! Membe r: Outside Consultant, Chemistry and Radiochemistry ALTERNATES 6.5.2.3 All 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 as voting members in ORC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC.
BEAVER VALLEY - UNIT 1 6-8 Amendment No. 46 Proposed Wording
I ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of f acility activities shall be performed un' der the cognizance of the ORC. These audits shall encompass:
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of oper-ation that affect nuclear safety at least once per 6 months.
- d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
- e. The Facility Emergency Plan and implementing procedures at least once per 12 months.
- f. The Facility Security Plan and implementing procedures at least once per 12 months. .
- g. Any other area of facility operation considered appropriate by the ORC or the Vice President, Nuclear,
- h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
- 1. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.
BEAVER VALLEY - UNIT 1 6-10 PROPOSED WORDING
ADMINISTRATIVE CONTROLS AUDITS (Continued)
AUTHORITY 6.5.2.9 Ths ORC shall report to and advise the Vice President, Nuclear Division on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated by the following:
- a. Minutes of each ORC meeting shall be prepared for and approved by the ORC Chairman within 14 days following each meeting.
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- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved, and forwarded to the ORC Chairman within 14 l days following completion of the review.
- c. Audit reports enecmpassed by Section 6.5.2.8 above, shall be for-warded to the Vice President, Nuclear Division and to the management positions responsible for the areas audited within 30 days after completion of the audit,
- d. The Vice President, Nuclear Division shall review all recommenda-tions of the ORC.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
- a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
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- b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by ths OSC and submitted to j the ORC and the Manager of Nuclear Operetions.
BEAVER VALLEY - UNIT 1 6-11 PROPOSED WORDING
I ATTACHMENT B Proposed Change Request No. 83 revises the Beaver Valley Power Station, Unit No. 1 Technical. Specifications Appendix A, Section 6 concerning OSC and ORC membership reorganization and to comply with Ceneric Letters 82-17 and 82-23.
Generic Letter 82-17 requires compliance with 10 CFR 50.54(t) in that each licensee shall provide for an independent review of its emergency preparedness program at least every 12 months. To comp 1i Section 6.5.2.8(e) of the Technical Specifications has been revised to require that an audit shall be performed of the Facility Emergency Plan and implementing procedures at least once per 12 months under the cognizance of the ORC.
Generic Letter 82-23 requires compliance with 10 CFR 73.40(d) l in that each licensee shall provide for an independent review of its safeguards contingency plan at least every 12 months. To comply Section 6.5.2.8(f) of the Technical Specification has been revised to require that an audit shall be performed of the Facility Security Plan and implementing procedures at least once per 12 moaths under the cognizance of the ORC.
Sections 6.5.1.6(1) and (j) have been deleted to reduce duplication of requirements. Review of the Plant Security Plan and implementing procedures 6.5.1.6(i) and review of the Emergency Plan and implementing procedures 6.5.1.6(j) are included under OSC review responsibility in Section 6.5.1.6(a), which requires the OSC to review all procedures required by Specification 6.8. Section 6.8 Procedures, requires pro-cedures to be established, implemented and maintained for:
6.8.l(d) Security Plan Implementation 6.8.l(e) Emergency Plan Implementation Seccion 6.5.1.2 OSC Membership, has been revised to include the Quality Control Engineer.
Section 6.5.2.2 ORC Membership, has been revised so that the ORC is now chaired by the Vice President, Nuclear Division. Other members have been changed to incorporate positions that have been filled as a result of the Nuclear Division reorganization.
Section 6.5.2.9 Authority, has been revised so that the Vice Preaident, l Nuclear Division has the responsibility for ORC authority.
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i 2-Section 6.5.2.10 Records, has been revised in sub-sections a and b so that the ORC Chairman is responsible for approving ORC minutes and reports of reviews encompassed by Section 6.5.2.7. Sub-section d was revised so that the Vice President, Nuclear Division reviews all ORC recommenda tions.
The revisions requested by this proposed Technical Specification Change do not increase the probability of an accident nor the con-sequences of an accident nor create the possibility of an accident different from those analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not reduced.
The OSC and ORC have reviewed this proposed change and based on the above safety evaluation, it is concluded there is reasonable assurance that the public hesith and safety will not be endangered by operation in the proposed manner.
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