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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PROPOSED CHANGE STATION ORGANIZATION SALEM UNIT NOS. l AND 2 TECHNICAL SPECIFICATIONS LCR NO. 80-11
.*. ~ .
- Description of Change
- *~~is change* provides for the *separation of the radiation protection function from the Performance Department and formation of a new Radiation Protection Department. This new department will be headed by a Radiation Protection
- Engineer *who will report directly to the station Manager.
___ It will have a Senior Supervisor - Radiation Protection (who will act as backup to the Radiation Protection Engineer),
Technical Supervisors, Technicians and Technical Assistants,
- fill ~f whom will be devoted to the function of radiation
--~protection.
- ---------"!1.'he .remainder of the Performance. Department .will be modified
- _ - :.to split the Technical Assistants such that they are devoted
- to either the instrumentation and controls function or the
Section 6.12 High Radiation Area, in the Salem Unit 1 Tech-nical Specifications will be changed to read identically to
-Salem Unit 2 Technical Specifications for consistency.
Reason for Change This change is being made to further increase the importance of the radiation protection function and to organizationally .'
meet the intent of Item 9.4 of Facility Operating License DPR-75, Appendix A. Prior to this.proposed change, the intent of Item 9.4 was met by a directive to the Senior Performance Supervisor - Radiation Protection that he shall report to the station Manager.
Safety Evaluation
_This change represents an upgrading of the importance of the
- _radiation protection function and is in compliance with the intent of Item 9.4 of the Facility Operating License, Appen-dix A, and the Safety Evaluation Report, Salem Nuclear
-_~nerating Station, Unit 2, Supplement 4, NUREG-0517, .
- .Section .12. 0 Radiation Protection.
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SALEM - UNIT 1 TECHNICAL SPECIFICATION CHANGES
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ADMINISTRATIVE CONTROLS 6.3 FACILilY STAFF (XJALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum
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qualifications of ANSI NlS.1-1971 for.cosnparable positions, excipt for the Radiation Protection Enaineer. . . who Shal 1 meet Or exceed the qualifications of f!.~ulatory Gulde 1.8. September 1975.
I 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by the Assistant to Manager and under the direction of the Training Engineer and shall meet or exceed the require-ments and recamiendations of Section 5.5 of ANSI NlS.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be lllintained under
the direction of the Safety Supervisor end shall meet or exceed the requirements of Section 27 of the NFPA Code-1975. except fer Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW ANO AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC}.
FUNCTION 6.5.1.1 The Station Operations Review Corrmittee shall function to advise the Station Manager en all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Station Operations Review Comnittee shall be composed of the:
Chainnan: Chief Engineer V1ce Chainnan: Assistant to Manager Member: Station Operating Engineer Member: Station Perfonnance Engineer Member: Reactor Engineer "ember:
- Senior Shift Supervisor .
Menber: Senior Performance Supervisor
- I&C Member: Senior Performance Supervisor - Chemistry
- Member: ~*Radiation Protection Enqineer I Member: Senior Maintenance Supervisor
- 1'1ember Maintenance Engineer
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ALTERNATES 6.5. 1 .3 Al 1 alternate members sha11 be appointed 1n writing by the SORC Chairman tc serve on a temporary basis; however, no more than two alternates shall participate as voting members in SORC activities at any one time.
SALEM-UNIT 1 6-5 Amendment No. Je. 11. 11.'J'
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ADMINISTRATIVE CONTROLS
- c. Records of facf Hty radiation and conµntinatimt surv.eys.
- d. Records of radiation exposure for all individuals entering radiation control areas.
- e. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facility components identified 1n Table 5.7-1.
- g. Records of training and qualification for current members of the plant staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- 1. Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews perfonned for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Records of meetings of the SORC and the NRB.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations fnvo1v1ng personnel radiation exposure.
6.12 HIGH RADIATION AREA
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SALEM-UNIT 1 6-15 ~endment No. ~
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ADMINISTRATIVE CONTROLS 6.12 HIG~ RADIATION AREA (Continued) 6~ 12 HIGH RADIATION AREA
-6.12.1 In lieu of the 11 control device" or "alarm signal" requ1r&d by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Exposure Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: -
- a. A radiation monitoring device which continuously indicates the radiation aose rate in the area.
- b. A Tadiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this 110nito~ing device may be aade after the dose rate level in the area has been estab-lished and personnel bave been 111de knowledgeable of them.
- *Radiation Protect.ion personne 1 or penonne 1 escorted by RiuHation Protection personnel
_- shall be exempt from the REP issuance requirement during the perfonDance of
- _ their assigned radiation protection duties, provided they comply with
--: *approved radiation protection procedures for entry into high radiation areas.
_SALEM-UNIT 1 6*16 Amendment No. 'J6
---;-------;:----------~ ----------------
AOMINIS~RATIVE CONTROLS
- c. An individual qualified in radiation protection procedures who fs equipped with a radiation dose rate aonitoring device. Thi* indi-vidual shall be responsible for providing positive control over the
- ctivitfes within the area and shall perfor111 periodic radiation
~urveillance at the frequency specified by the Senior Pe: ill"MIACe Supervisor - &t1emfiti1P in the Radiation Exposure Pennit.
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- 6. 12.2 The requirements of 6. 12. 1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.
In *ddition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Senior Shift Supervisor on duty and/or the Senior Supervisor - Radiation Protection S Iii. E. Y, - LI IJ IT I
SALEM - UNIT 2 TECHNICAL SPECIFICATION CHANGES
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ITATION P'EAFORMANCI INOINtEA llADIATIOll
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.. FIGURE 6.2.21 FACILITY ORGANizATioM SALEM GENERATiltG STATION
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3. 1 Each aember of the facility staff shall aeet or exceed the *1n1mum
____ _.Quali.ftc_at_ions of ANSI NlS.1-1971 for comparable positions, except for the Radiation Protection Engineer qualifications of Regulatory Guide l.8 who shal 1 meet or exceed "the Septelllber 1975.
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-6.4 TRAINING 6.4. 1 A retraining and replacement training program for the facility staff shall be coordinated by the Assistant to Manager and maintained under the direction of the Training Engineer and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18. 1-1971 and Appendix 11 A11 of 10 CFR Part 55.
6.5 REVIEW ANO AUDIT 6.5. 1 STATION OPERATIONS REVIEW COMMITTEE (SORC)
. FUNCTION _
~.5. 1. 1 The Station Operations Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.
COMPOSITION 6.5. 1.2 The Station Operations Review Committee shall be COlllposed of the:
Chairman: Chief Engineer Vice Chairman: Assistant to Manager Member: Station Operating Engineer Member: Station Performance Engineer Member: Reactor Engineer Member: Senior Shift Supervisor Member: Senior Performance Supervisor - l&C Member: Senior Performance Supervisor - Chemistry
Member:
Radiation Protection Engineer Senior Maintenance Supervisor I
Member: Maintenance Engineer ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the SORC Chairaan to serve on a temporary basis; 'however, no more than two alternates shall .participate as voting aembers in SORC activities at any one time.
MEETING FREQUENCY 6.5. 1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.
SALEM - UNIT 2 6-6
ADMINISTRATIVE CONTROLS
- e. Records of transient or operational cycles for those facility compo*
nents identified in Table 5.7-1.
- f. Records of reactor tests and experiments. ...
Records of training and qualification for current members- of the
~- .- -**
. *-.-----********** ... *- _plant staff.
- -:--;--'-:*~ b. Records of in-service inspections performed pursuant to these Tech-nical Specifications.
- 1. Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews perfonned for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR S0.59.
-t. :.clecords of 11eet i ngs of the SORC and the NRB.
~. 11 fW>IATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent
_-.with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or "alarm signal" requi~d by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a High Radiatfon Area and entrance .
thereto shall be controlled by issuance of a Radiation Exposure Permit*. Any individual or group of individuals permitted to enter such areas shall be
. provided with or accompanied by one or more.of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b. A radiation aonitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this inonitoring device
- ay be aade after the dose rate level in the area has been estab-lished and personnel have been aade knowledgeab1e of them.
'* Radiation Protection _personne 1 or personne 1 escorted by Radiat.ian Protection personnel I sba11 be exempt from the REP issuance requirement during the perforaance of
~ their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SALEM - UNIT 2 6*18
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4 ADMINISTRATIVE CONTROLS
- c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform periodic rad1ation surveillance at the frequency specified by the Senior Pef"fo*fllli8Me Supervisor - ~P in th~ Radiation Exposure Permit.
l::At:J1119770A-1 l""'l2oT7c.7?o.!V
- 6. 12.2 The requirements of 6. 12. 1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Senior Shift Supervisor on duty and/or the Senior Supervisor.. - Radiation Protection SALEM - UNIT 2 6-19