Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18107A5171999-08-25025 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 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 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 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 ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 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 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 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 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 ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 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. 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 ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6081997-10-0606 October 1997 Proposed Tech Specs Revising LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5571997-08-27027 August 1997 Proposed Tech Specs,Providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, Which States That Three CCW Pumps Required to Meet LCO ML18102B5301997-08-19019 August 1997 Proposed Tech Specs,Providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Salem Unit 2 ML18102B5341997-08-18018 August 1997 Proposed Tech Specs,Incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4891997-08-0101 August 1997 Proposed Tech Specs Section 4.2.1 Rewording Section to State Util Will Adhere to Section 7,Incidental Take Statement Approved by Natl Maring Fisheries Svc ML18102B3911997-06-12012 June 1997 Proposed Tech Specs,Representing Addition of New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B3061997-05-14014 May 1997 Proposed Tech Specs,Revising SR 4.7.6.1.d.1,to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & Reflecting Filter Dp Acceptance Value Greater than 2.70 Water Gauge ML18102B2631997-05-0101 May 1997 Proposed Tech Specs,Adding New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B2601997-05-0101 May 1997 Proposed Tech Specs 3/4.7.7 Revising Certain Allowed Outage Times & Creating 3/4.7.11 to Address Switchgear & Penetration Area Ventilation Sys ML18102B0341997-04-25025 April 1997 Proposed Tech Specs 3.5.2 Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 1999-08-25
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program 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 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 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 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 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 ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 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 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 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 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 ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm 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 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. 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 ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 1999-09-10
[Table view] |
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Document Control Desk LR-N96264 Attachment 1 LCR S96-11 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS BASIS FOR REQUESTED CHANGE REQUESTED CHANGE AND PURPOSE The changes identified on Attachment 3 will remove the indicated License Condition from the Facility Operating License for Salem Unit 2. This is TMI Action Plan Item I.A.1.3 - Shift Manning.
Specifically, the condition states, "PSE&G shall establish regularly scheduled 8-hour shifts without reliance on routine use of overtime by June 3, 1981. 11 PSE&G is proposing to delete this license condition. PSE&G is also proposing to modify Technical Specifications (TS) Section 6.0 Administrative Controls to incorporate shift manning and limits on overtime. This will allow the continued use of a regularly scheduled 12-hour shift rotation without routine heavy use of overtime. In addition, TS 6.2.2.d identifies that PSE&G's limits on overtime are defined in Generic Letter 82-12.
BACKGROUND PSE&G has established a 12-hour shift schedule for the Hope Creek Nuclear Station. This schedule was approved by the NRC in Amendment 41 to the Hope Creek TS. PSE&G has also established a 12-hour shift rotation for Salem Nuclear Generating station.
However, it has been identified that the Salem Unit 2 Facility Operating License DPR-75 contains a license condition that stipulates 8-hour shifts. PSE&G is proposing to delete this license condition and incorporate the requirements with a change to 12-hour shifts into the Administrative Controls section of TS.
Salem Units 1 and 2 are currently shutdown and defueled. PSE&G will continue to operate on the established*12-hour schedule.
Transition to a different shift rotation at this time would disrupt the current outage schedule and affect the manpower available to augment outage support.
r-1 9609040267 960827 PDR ADOCK 05000272 I p PDR
Document Control Desk 2 LR-N96264 LCR S96-11 JUSTIFICATION OF THE REQUEST CHANGE 12-hour shifts provide for a reduced number of turnovers which allows for better communications and continuity. Shifts are trained as a team, and a change to 8-hour shifts would disrupt the team concept that has been established.
The current 12-hour shift schedule has enjoyed a high-degree of acceptance among shift personnel, both workers and supervision alike. On the 12-hour shift schedule, personnel receive more consecutive time off, therefore, they are more rested when returning to work. There is less changing of shifts and therefore, personnel have sufficient time to adjust to the changes.
The change to the specifications will not allow routine use of overtime. In addition, TS 6.2.2.d identifies PSE&G's limits on overtime. The specification refers to Generic Letter 82-12 which defined appropriate limits on overtime for operating personnel.
The limits specified in the generic letter are defined in PSE&G Nuclear Business Unit's Administrative Procedures.
CONCLUSION Based on the above discussions and the no significant hazards consideration determination presented in Attachment 2, PSE&G has determined that the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard and are therefore acceptable.
Document Control Desk
- LR-N96264 LCR S96-11 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS 10CFR50.92 EVALUATION Public Service Electric & Gas company (PSE&G) has concluded that the proposed changes to the Salem Generating Station Unit 2 Facility Operating License and to the Salem Units 1 and 2 Technical Specifications(TS) do not involve a significant hazards consideration. In support of this determination, an evaluation of each of the three standards set forth in 10CFR50.92 is provided below:
REQUESTED CHANGE The proposed change to the Salem Unit 2 Facility Operating License deletes license condition 2.C(24) (a) Shift Manning. This condition, TMI Action Plan item I.A.1.3, required PSE&G to establish regularly scheduled 8-hour shifts without reliance on routine use of overtime by June 3, 1981. PSE&G initially complied with the condition as required, however, PSE&G has since established a 12-hour shift rotation that does not rely on regularly scheduled overtime. PSE&G is also proposing to modify Salem Units 1 and 2 TS, Section 6.0 Administrative Controls, to incorporate shift manning while changing from 8-hour to 12-hour shifts.
BASIS
- 1. The proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
The proposed change does not involve a physical or procedural change to any structure, system, or component that significantly affects the probability or consequences of any accident or malfunction of equipment important to safety previously evaluated in the Updated Final Safety Analysis Report (UFSAR). The proposed changes will permit the use of 12-hour shifts which average 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week and also satisfy the guideline in Generic Letter 82-12 for operating shifts.
This change is administrative in nature and has no significant impact on the probabilities or consequences of any evaluated accident or malfunction of safety important equipment.
Document Control Desk 2
- LR-N96264 Attachment 2 LCR 896-11
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed revision involves no physical changes in the plant or to the manner in which plant systems are operated.
The change modifies the working hours per shift for operating personnel without significantly changing the hours worked per week and retains the current limitations on excessive overtime. The proposed changes are administrative in nature; therefore, no new or different accident is created.
- 3. The proposed change does not involve a significant reduction in a margin of safety.
This is an administrative change and does not affect any margins of safety. Plant operation with the proposed revision to shift working hours has been found to improve operator morale and performance.
CONCLUSION Based on the above discussion, PSE&G has determined that the proposed changes do not involve a significant hazards consideration.
Document Control Desk LR-N96264 LCR 896-11 MARKED UP PAGES
ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The facility organization shall be subject ~~ the fo:..lJwing:
- a. Each on duty shift shall be composed of at least the minimum shift c::-ew composition shown in Table 6. 2-l;X". ~
- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times.
- c. All CORE ALTERATIONS shall be observed and directly super*.rised by a licensed Senior Reactor Operator who has no other concurrent responsibili~~es during this operation.
- d. The amoi..:...~t ct overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy St:,:; ~.::rnent on working ~ours (Generic i:.er.r:.er No. 82-12)
- e. The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor cperatcr license. 7he Nuclear Cor.:rol Operators shall hold reactor ooerat::::r lice:i.ses.
- f. The Opera:ions Manager shal:.. rnee: or.e cf the following:
\1) Ho:..~ an SRO 2.i::::e::;se.
(2) Have held ar. SRO 2.i:::ense f::Jr a s1m12.ar ur.it :?WR).
Q..,j e be.
Ad e ~ ua..-+e .sh 1-4'-t C'c*v'e1 0 \..' c::: l t r{Y) e w 1Tho~T roLJt1ne.. he11.- y i.' u I o1e.r ~ -t lo S (:)er soi'" o e }
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()Orr>1no....j l ) \"I I t I $;" o pero... ti().1, SALEM - UNIT 1 6-2 Amendment No. 168
(21 l Sum~ ~erfol""1ance (Section 6.3.3, Suoolement Sl (al Prior to resuming power opera ti on fo 11 o"'i ng tl'le first refueling outage, PSE!iG shall provide a detailed survey of insulation :naterials.
(bl Prior to operation above fi'le ;Jercent power, control ruom operators shall be trained in the recognition and mitigation of l?! performance de9radation.
(22) Radiation Protection Oraan.ization (Section 12.0, Suoolement Sl PSE&G shall c:Jnplete the reorganization actions and programs associated with radiation protection no later than November l, 1981.
( 23 l Category r 1'4asonry '..Ja 11 s (Section 3 .8 .3, Suoo l ement S)
(al Prior to operation above f'fve oen:ent power, PSE!iG shall submit the information requested in the NRC letter dated January 8, 1981.
( b) Pri o,. to startup fo 11 owing the first refuel i ng, PSBG sna 11 resolve the difference bet'#een the staff criteria and the criteria used by PSE&G to the satisfaction of tl'le NRC and implement tl'le required fixes tl'lat ~ight result fran such a re solution.
(24) TI4I Action P1an Conditions (Section 22.2, Supplement 5)
Unless other-.ise noted, each of the following conditions references the appropriate section of Supplement No. 5 to the Safety Evaluation Report (NUREG-0517) for the Salem Nuclear Generation Station, Unit 2, dated January 1981 and shall be completed to the satisfaction of the NRC by the times i ndi cate<1.
PSE&G u arly scheduled eight-nour (b) Shor~-ienn lccicent ~nalysis and ~r~cedure ~evision
( ~ ei::: ~ on 22 . 2 , ! . C. l and : . ~
7he ocerator! s~all be briefed on tne revisions ~o :ne
- mer'1ency ocerJtion instr*.Jct~on *..-itnin 30 effective f'lil
~ewer days of operation.
ADMINISTRATI'Ve: CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and snall 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 Nuclear Officer and President - Nuclear Business Unit, shall be reissued to all station.personnel on an annual basis.
I.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite 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. ~hese relationships shall be documented and updated, as appropriate, in the form ~f organization charts, functional descriptions of departmental r~sponsibilities and relationships, and job descriptions for key personnel positions, or in equivalen=
forms of documentation.* These requirements shall be documented ~~
the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).
- b. The General Manager - Salem Operations shall be responsible for overall facility safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plants.
- c. The Chief Nuclear Officer and President - Nuclear Business Unit shall have corporate responsibility for overall plant nuclear safety 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 cruality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
f"'c..ve 6.2.2 FACILITY STAFF
-to 0e.ft"
~e.. The Facility organization shall be subject to the following:
~u... J
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. T,._;.sE:Q..1 J SALEM - UNIT 2 6-1 Amendment No. 150
.b; At least cne licensed :Reactor cpttator shall be in the cx:a1t:rol ro::::m
- when fuel is in the reactor. In ad:litiat, at least cne lioersed Senior Reactor q:ierator shall be in the a:rrt:.rol Rcan area at all tilll!!S.
- c. All a:m: ~CNS shall be c:i::1Served an:i directly supmvise:i by a licensed Senior Reactor ~tor who has no other ccn::urrent respcnsibilities during this cperatiat.
- d. 'Ihe mmt of overtime W10rlced by plant staff ne** et'S perfomin; safety-related fun:::ticns DJSt be l.iJDit:ed in acx::crdance with the NRC Policy statement cri workin; hairs (Generic Letter No. 82-12).
- e. 'Ihe ~tin; Erqineer, Senior Nlci.ear Shit't SUpervi.scrs, ani Nlci.ear Shift .SUpervisors shall each hold a senior reactor cperator lioen;e. 'lbe Nllcl.ear a:ntrol cpttatcrs shall hold reactor c:p!rator lioerises.
- f. 'Ihe cp!raticns Manager shall meet cna of the followi.n;:
(1) Hold an SR:> license.
(2) Have held an SR:> liamse for a similar unit (~).
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Li.)01 k t LS ev ri o {'r')I n a.... I C) ref<l., t.i{) 5 I SAUM - UNIT 2 6-2 Amen::lme It No, il I