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] |
Text
The following pages are proposed changes to the Unit 1 Technical Specifications:
ViCI! l're91dent
-rue1 Gerer111l
""1la9er -ruelSWly I N General Manaqer -Pn:xb:tion SUl:DJrt.
Gener11l Manaqer -Corporate
()lality Assurance l'l.lc. Plant fn1r. Asst, Vice President
-Pto:tucticn M:Jr. -Per9CR'!el Aff11lni ' 1dnWstr11ticn Training MaMqer cter. suwart tb:\Pllr f'iel cycle Dli1r. Hi!Alth Physicist Senior Vice l'rPsldent
-
SUWly ard Enlinocrinq Vice l'nl*ident
-Pra!octi.on
,.--L-General M.'Ullllqer
-Nuclear rroduction DP.rg. Plaminq ' S<.>nlt'ity Dqr.
- UceMinq and Envlr<nrent r--------1 On-Site I Safety .,_ _____ _. Review I Group ** Requlatory Affain M!lnaqer -Salm Gereratinq Station Lioenlling md AMlyaie L ______ _ *
- U\i t 2 i-.quinm!nt II Direct """""" for tllm'C}SlCY FIGURE 6.2-1 OFFSITE ORGANIZATION FOR FACILITY MANAGEMENT AND TECHNICAL SUPPORT -------*-------
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I ASSlSTANT TO MANAGER STATION OU ALI TY ASSURANCE ofillUiOIH A ** . --, f. I SECURITY SAFETY SUPERVISOR SUPERVISOR CTOA OPERATOR SRO -SENIOR REA RO -REACTOR 0P£ RA TOA ..
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f ** Proiecuon Plot11*m REACTOR ENGINEER I SHIFT TECHNICAL ADVISORS ITAFF _ ---St;""N 00#-J tMf *011 be C ldc.u 7M11t11':3 cs c .(
-.t-MANAGER-SALEM GENERATING STATION
- CHIEF ENGINEERt STATION OPERATING ENGINEER t SENIOR SHIFT SUPERVISOR-SRO SHIFT SUPERVISOR-SRO CONTROL OPERATORS-RO EQUIPMENT OPERATOR I UTILITY OPERATORS I I I II r I . I Ot°F S1r£ 1 I I SORC I I_----'--** I I I I ---I ----. ------T I I I I I l I I STATION RADIATION PEHFOHMANCE PROTECTION ENGINEER ENGINEER I SENIOR SENIOR :r"Y-C.
SENIOR OT.' SUPERVISOR
-SUPERVISOR-SUPERVISOR
-RM. PflOT. ..,.. QtiUl&lR¥ I 16C SUPERVISOR OtEMISTRY RAD. PROT.
SUPt'* I l*C CHEMISTRY RAD. l'ROT. TECHNICIANS TECHNICIANS TECHNICIANS I 16C CHEMISTRY RAO. PROT. ASSIST ANTI ASSlSTANTI ASS.IST ANTI I I TECH. HEU'ER -NUCLEAR RAO.PROT.
HELPER 'f4c , S .J.Ao f ION FIGURE 6.2.2 FACILITY ORGANIZATION
-SALEM GENERATING STATION , ' ' MAINTENANCE ENGINEER .... ADMIN TRAJOR SENIOR MAINTENANCE SUPERVISOR MAINTENANCE OFFICE SUl'ERVISOA SUPERVISOR OOILEA REPAIR MECHANIC STAFF ELECTRICIANS MACHINISTS STATION MECHANICS UTILITY MECHANICS
- ---*---*
(" \_ -* ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.l Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI NlS.1-1971 for comparable positions, except for the Senior Perfonnance Supervisor
-Chemistry/HP who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septenber 1975. --6.4 TRAINING e.4 c..4 llVfc.i/ou I
c-,_ (d/'._,,.(,,.,_
... /4. r4. c I/, i.:y A retraining and training program for the facility staff shall be coordinated by and under the I direction of the Training
- and shall meet or exceed the require-ments* and
- 5. 5 of ANSI Nl8. 1-1971 and Appendix 11 A 11 of 10 CFR Part 55.
'-r 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Safety Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW
AND AUDIT 6:5.l STATION OPERATIONS REVIEW COMMITTEE (SORC) FUNCTION 6.5.1.1 The Station Operations Review Corrmittee shall function to advise the Station Manager on all matters related nuclear safety. COMPOSITION 6.5.1.2 The Station Operations Review Committee shall be composed of the: Chainnan:
Chief Engineer Vice Chainnan:
Assistant to Manager Member : Station Operating Engineer * :Member: Vi'c.e. Station Perfonnance Engineer t Member: Reactor Engineer Member: Senior Sh" t upervisor Menber: Senior y-. . Supervisor
-I Member: Senior "* Supervisor
-
Member: 1f.1:l
... Se11im Member: Senior Maintenance Supervisor
_ ...f!o!eu'*wr c.Jv.;,.-;.
1111 Maintenance Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman to 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. Hl, 1J, n, 25
- '* *-e ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chainnan or his designated alternate.
--QUORUM 6.5.1.5 A quorum of the SORC shall consist of the Chainnan or his designated alternate and four members including alternates.
RESPONSIBILITIES The Station Operations Review C0ntnittee shall be responsible for: a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as detennined by the Station Manager to affect nuclear safety. b. Review of all proposed tests and experiments that affect nuclear safety. c. Review of all proposed changes to Appendix 11 A 11 Technical Specifications
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recor.mendations to prevent recurrence to the General Manager -Ele:zt14<:
Production and to the Chainnan of the f Nuclear Review Board.
- f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Comnission.
- g. Review of facility operations to detect pote*ntial nuclear safety hazards. h. Perfonnance of special reviews, investigations or analyses and reports thereon as requested by the Chainnan of the Nuclear Review Board. SALEM-UNIT 1 6-6 r--( /
- CONTROLS i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board. j. Review of the Emergency Plan and implementing procedures and shall submit recOIJlllended changes to the Chairman of the Nuclear Review Board. AUTHORITY 6.5.1.7 The Station Operations Review Corranittee shall: a. b. Reconmend to the Station Manager written approval or disapproval of items considered under 6.5. l.6(a) through {d) above. Render detenninations in writing with regard to whether or not each item considered under 6.5.l.6(a}
through (e) above constitutes an unreviewed safety questicn.
- 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 General Production and the Nuclear Review Board of f disagre e "e'fween the SORC and the Station Manager; however, the Station Manager shall have responsibility for.resolution of such disagreements pursuant to 6.1. 1 above. RECORDS 6.5.1.8 The Station Operations Review Corrmittee shall maintain written minutes of each meeting and copies shall be provided to the General Production and Chainnan of the Nuclear Review Board. / /Y .. ""I <!!A ,-6.5.2 NUCLEAR REVIEW BOARD (NRB) FUNCTION 6.5.2.1 The Nuclear Review Board shall function to provide independent review and audit of designated activities in the areas of: a. nuclear power plant operations
- b. nuclear engineering SALEM-UNIT 1 6-7 I -,. --*, ADMINISTRATIVE CONTROLS c. chemistry and radiochemistry
- d. metallurgy
- e. instrumentation and-,ontrol
- f. radiological safety g. mechanical and electrical engfoeering
- h. quality assurance practices COMPOSITION 6.5.2.2 The NRB shall Chainnan:
Vice Chairman:
Member: Member: Member: Member: Member: Member: Member: . ALTERNATES be composed of the: .. ,4.ss1$. fA1t i-f/icc
- .de,., t -Pr,;.r
- L.::
/-' ' Gc::et a1 ltaAageP =El cc ta i c P1 odac ttl:m
- Assistant to General Manager-Fuel Supply General Manager-Licensing and Environment Manager-Nuclear Operations
..S'Y'/"r -e Mae 1ge1 -Qaal i CJ "Assara11'e G-r:J.en I /l'!A .. /4',
6' l'1 '* '1jed
.. //ltw.;v-A/;._.
/,,.,.
Manager-Salem Generating Station Principal Engineer Manager -Hope Creek Generating Station 6.5.2.3 All alternate members sha11 be appointed in writing by the NRB Chainnan to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB. MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
SALEM ... UNIT 1 6-8 Amendment No. 11; 25
{ \ .e * **** ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NRB activities shall be prepared, approved and distributed as indicated below: a. Minutes of each NRB meeting shall be prepared, approved and forwarded to the Vice President-Production within 14 days fol lowing each meeting. b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President-. Production within 14 days following completion of the review. c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Production and to the management positions responsible for the areas audited within 30 days after completion of the audit. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.l 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. 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 the SORC and submitted to the NRB and the General Manager-Elwct1 ic Production.
I 111 ....
,-SALEM-UN IT 1
- -* DMINISTRATIVE CONTOLS 5.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The facility shall be placed in at least HOT STANDBY within one hour. b. The Safety Limit violation shall be reported to the Corrmission, the General Manager4l-0eti FE; Production and to the NRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. AA..:.k=A-
- c. A Safety Limit Violation Report shall be prepared.
The 0 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 Report shall be submitted to the Commission, the NRB and the General Production within 14 days of the violation.
6.8 PROCEDURES
6.8. 1 Written procedures shall be established.
implemented and main-* tained covering the activities referenced below: a. The applicable procedures recon1T1ended in Appendix "A" of Regulatory Guide 1.33, November, 1972. b. Refueling operations.
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation.
- e. Emergency Plan implementation.
- f. Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the SORC and approved by the Station Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
SALEM-UNIT 1 6-12 Amendment No. 11 I