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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML20206T8941999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9 ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML20206G2281999-03-31031 March 1999 Rev 18 to ODCM for Hope Creek Generating Station ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements 1999-09-30
[Table view] |
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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 0,--6-. .-1--T-h-e.ft~J,_G_e_IJ_.e_r_a_l_M_a_TI_.a_g_e_r__S_a_l_e_m_,_o_p_e_r_a_t_i_o_n_s: :p-: -:J: :t,.): : Jt-: -i1\-: -#: :':':\: :\:i,¥-: -,~-: -:'p: :;'i: :}-: -?#.: :~: :\¥,'I: shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Chief Nuc 1 ear Off i ccr and rPcrci* ss siudccndtto ~af'lucl 1 cs atartBi* *ouns ipnccrs ss ounnncitl§~o;:;;:µ;n:::}i;P.a:::;:Jn:J:\]ca;:}nZ:l:tP:n;:;::u:*::;;P.a:Jil:}r:mf\W:
w@@i!imi~%\f9\l\l\ffi~:~% I shall be basis.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsitc and offsitc organizations shall be established for unit operation and corporate management, respectively. The onsitc and offsitc organizations shall include positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined from the highest 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 descriptions 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 Salem Updated Final Safety Analysis Report and updated in accordance 7
~~~~b-.~~:-:-*:h~~~~:-:-c-:-:-:-:-:-n-*a--:-~-:-l-*_s_a_l_c_m_,_O_p_c_r_a_t_i_o_n_s_~-*-Ji-J~-f-i-ij-~-~-.-,-~-~-!H~!lshall be responsible for overall facility safe operation and shall have control over those onsitc activities necessary for safe operation and maintenance of the plants.
- c. The Chief Nuclear Officer and President nuclear Business Unit
$.@i.M~@Ji\#\i.ii.M#i.#ili.\':Jii.#@M#.fa\\\\@:~\~\~§~:#,' shall have corporate responsibility for overall plant nuclear saf cty and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plants to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsitc manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
FACILITY STAFF The Facility organization shall be subject to the following:
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
SALEM - UNIT~--- --- t::-1 Amendment No. ~
9603050136 960226 PDR ADOCt~ 05000272 P PDR
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ADMINISTRATIVE CONTROLS
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RECORDS MID REPORTS 6.5.3.4 Written records of reviews perforFRed in accordance with .:..teFR G.5.3.2a above, including recoFRFRendations for approval or disapproval, shall be FRaintained. Copies shall be provided to the General Manager SaleFR Operations, SORG, the OSR staff and/or :NRG as necessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and/or a report submitted pursuant t3:::fhe r *r e ct* on 0 'J to lOC ~t 50, and C2',~~ 6/e/'f.4tat)'VS "l?"f'V* etV Cp>.mm/ ee CU:>/f'C-;?.__;]
- b. Each REPORTABLE EVENT shall be reviewed by the &GF£ and the~~~-----
resul tant Licensee Event Report submitted to the s aff and the Chief Nuclear Officer and President Nuclear Business Urlit$.i;#ii:$P:#
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6.7 SAFETY LIMIT VIOLATION
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(_,,~ __,____:_,...--"--~---~__.,------
- 6. 7. l 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.
- b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Chief Nuclear Officer and President ~ruclear Business Unit ih¥ridiBf:6d't.8:'.biBe nudlfifa{f'fo:ti .::':'?:":':\ and
- -~-~-mt~
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Re ort shall be submitted to the Commission, the Director Quality Assurance and Nuclear Safety
~--~-***
ih;:9*;;*~;;99****anit ~:~n,$$%J:sam8!~~3l:P.?9+/-!#-J!:§f'.%:!:83!
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within 14 days of the SALEM - UNIT 1 6-16 Amendment No. -3:-6-ADMINISTRATIVE CONTROLS
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RECORDS MID REPORTS 6.5.3.!l: Written records of reviews performed in accordance with item G.5.3.2a above, including recoffiffiendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Hanager Salem Operations, SORG, the OSR staff and/or "NRG as necessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. submitted pursuant b.
and the 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.
- b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Chief :Nuclear Officer and President Nuclear Business Unit ifl~h+/-8.:h%i:iii'lf.\foiate niic'lMaE/6.f=:lrnk:e*Faa;.n~dITT~g~~=~~~~~~~~~~~~~~~~~~~~;==f
~;,~;,~~~iii~iilli1111~11111111111111111111111~~111111:¥::f,~f:@#ii##:m Wv¢=f:$.l§ll.i't shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
the violation.
SALEM - UNIT 2 6-16 Amendment No. ~
ADMINISTRATIVE CONTRO~
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cross disciplinary review is Reeessary. If deemed Reeessary, such review shall be performed by the appropriate desigRated review personRel. The StatioR Qualified Revie*.,,.ers shall FReet or eJEceed the qualifications described iR SeetioR 4.1 and 4.7 of rurn 3.1, 1981.
- d. If the Department Manager determiRes that the doeuFReRts involved require a 10 CFR 50.59 safety evaluation, the doeuFRcnts shall be forwarded for SORC review aRd also to the OSR staff for aR iRdcpendent review to determine whether or Rot aR uRreviewed safety question is involved. PursuaRt to 10 CFR 50.59, NRC approval of items iRvolviRg unreviewed safety questions or requiring Technical Specification changes shall be obtaiRed prior to implemeRtatioR.
~iON PROCEDURE RELATED DOCUMENTS
- 6. 5. 3. 3 Tests or eJEperiments, aRd changes to equipFReRt or systems shall be forwarded for SORC review and also to the OCR staff for an independent review to determine whether or not an unreviewed safety question is involved. The results of OSR staff reviews will be provided to SORC. Recommendations for approval are made by SORC to the General Manager Hope Creek Operations.
Pursuant to 10 CFR 50. 59, NRC apprO"J'al of items involving uareviewed safety questioas or requiring Technical Specification changes shall be obtained prior to implemeatation.
RECORDS MID REPORTS 6.5.3.4 Written records of reviews perforFRed iR accordance with item 6.5.3.2a above, including reeommendatioas for approval or disapproval, shall be maiataiaed. Copies shall be provided to the General Manager Hope Creek Operatioas, SORC, the OSR staff, aad/or ~me as aeeessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified pursuant to the requirements Section 50.72 to 10 CFR Part 50 and a report submittal pursua the requirements of Section 50.73 to 10 CFR Part 50,
- b. Each REPORTABLE EVENT shall and the results and the ehle£.
Nti~=etiT--9H+/-!e!~~:t--,PTes+/-fCTrt---N:t:te+/-etti:'-fffi.f:H::Jffi:e-s-s--tl~*:-t-**$#,!§@!i!11!1§g#gpt;jji\#@
6.7. SAFETY LIMIT VIOLATION 6.7.l The following actions shall be taken in the event a Safety Limit is violated:
- a. The NRC Operations Center shall be notified b ,;....;._;....~.__~..;..;_;...,_.....;;..;~-"=--=-~=-~"-----.
possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The uue 1 ear Bus inc s s Uni tifaiirididEJ8BiC:*]fai'ihfUitid:t\ifa{BJ d:f:f:ifcef0 notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
HOPE CREEK 6-14 Amendment No. t i