Proposed Tech Specs,Revising Administrative Controls for Plant Operations Review Committee & Nuclear Safety Review Board Composition & AlternativesML20011D435 |
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South Texas |
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Issue date: |
12/18/1989 |
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HOUSTON LIGHTING & POWER CO. |
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Shared Package |
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ML20011D434 |
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NUDOCS 8912270212 |
Download: ML20011D435 (7) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 ML20199A6101997-11-0505 November 1997 Proposed Tech Specs Pages,Updating TS Bases Section 3/4.4.9, to Reflect Results of Revised Analysis That Was Reviewed & Accepted by NRC as Part of License Amends 55 & 44.Analysis Results Not Incorporated Into TS Bases Due to Oversight ML20210T7401997-09-0404 September 1997 Proposed Tech Specs,Revising TS to Allow Use of Elbow Tap Differential Pressure Measurements Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ML20217M8351997-08-18018 August 1997 Proposed Tech Specs Incorporating Revs to TS 3.7.1.6, Atomospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Mode 1 & 2 ML20210L5801997-08-14014 August 1997 Proposed Tech Specs Allowing Tolerance of RCS Volume Provided in Specification 5.4.2 to Account for SG Tube Plugging ML20198F2211997-08-0505 August 1997 Proposed Tech Specs,Providing Suppl Info Re Amends to Licenses to Convert STP TS to Improved STS Format ML20148G1531997-05-29029 May 1997 Proposed Tech Specs Providing Administrative Changes to Affected Page Re Removal of Surveillance Requirement 4.7.7.e.5 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999 Rev 4 to Severe Weather Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20210J0481999-07-28028 July 1999 STP Unit 1,Cycle 9 Startup Testing Summary Rept ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 1999-09-08
[Table view] |
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ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION 6.5.1.2 T
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6.4.1 A-retraining and replacement-training program for the unit staff shall ;
,, be maintained under the direction of the Training Manager and shall meet.or
- exceed the requirements and recommendations of Section 5.5 of_ ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and ti.e supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28. 1980 NRC letter to all- licensees, and shall include familiarization with relevant industry operational experience. ~
6.5 REVIEW AND AUDli 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) 3 FUNCTION 6.5.1.1 The P0FC shall function to advise' the Plant Manager on all matters' related to nuclegsafetg 4g ,4 p g a ,, g COMPOSITION Svea oR e v svrsa,<s ope.Jh weinc o wu rE s io<os4c.skr a rresw.sg nes,#,Mg
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L euf <we<<<'9 cmbrow,Lm,As ek ar , opi am,,ee p,g ,jta l' 6.5.1.2 The PORC shall be composed of thr:g5*4hassw.:.ee4/p <j va p% 4
( ), ' e ,, '
L ember: 7E ed<frepres@Js nt Superintendent assve-ca y/g/x ,g y d4 .e, M mber: Tec a1 Services Manager cpp ,.4,f. J u gc, He er: Plant op tions Manager-4 *'-
j 4., Me er: Plant Engine ng Manager
- Mem er: Maintenance Man Mem r: Quality Engineer ng ager The PORC Chairman shall be appointed in writing from anone these members by the Plant Managegl=ri er re i=2m. Easta;;rine "crerJ -!! iS 4
-Teeimics 'arvie:f .".eneger dx; r.etweet ti.e ;n".'ic th ; :T : PM! tf en -
-Pret::tien Nr.e v ., e; &fk:d b 0;pkte , GuiA 1.6 (Ter;;;;;l 'al dien er.d ,
?? h; 0;; hie., i 0, tr.:: tre TenC waaiden wiii indva U 6.lttc j ;
??,eie* knovs' . hove kf k ppmj,,g sw& yge ,.asy[yQ ALTERNATES MMQ[j "' 'M'O '
3 h 6.5.1.3 All alternate members shall be appointed in writing by the Plant L . Manager to serve on a tesporary basis; however, no sore than two alternates shall participate as voting members in PORC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the- PORC Chairman or his designated alternate.
. QUORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three other members including alternates.
SOUTH TEXA5 - UNITS 1 & 2 6-7 Unit 1 - Amer dment .10. 4
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SICNIFICANT HAZARDS EVALUATION FOR A PROPOSED CHANGE IN.THE o .- NUCLEAR. SAFETY REVIEW BOARD COMPOSITION AND ALTERNATES a ,
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ST-HL-AE-3216 .
ff. Page 1 of 2 ATTACHMENT 3 SIGNIFICANT HAZARDS EVAI,UATION FOR A PROPOSED CHANGE IN THE -
NUCLEAR SAFETY REVIEW BOARD COMPOSITION AND ALTERNATES Backcround Technical Specification 6.5.2.2 requires that the Nuclear Safety Review Board (NSRB) composition consist of managers by specific title. The specific titles include the General Manager NSRB, General Manager S<.uth Texas Project Managoment, Vice President Nuclear Plant Operations, General Manager Nuclear Assurance and General Manager South-Texas Project Operations Support. .Several of the management titles listed are no longer in use at STPEGS.
Proposed Chance-Delete specific management titles from Technical Specifications and add '
a description which ensures top level functional area managers compose the NSRB (Attachment 6). .
Safety Evaluation In an effort to avoid future administrative Technical Specification changes when organization evolutions occur, specific etanagement titles for the composition of the NSRB should be avoided. The proposed changes ensure the level and range of expertise is maintained in the composition of the NSRB.
This is accomplished by requiring a full time NSRB chairman and four senior top-level functional area managers as members of the NSRB. These proposed changes vill allow HL&P and NRC resourcos to be better utilized on more important safety issues instead of utilizing resourcer on administrative Technical Specification changes. This proposed change will allow organization evolutions to occur without requiring Technical Specification changes.
Members of the NSRB will be qualified in accordance with ANSI 3,1-1981 and Regulatory Guide 1.8.
Determination of Sienificant Hazards Pursuant to 10CFR50.91 this analysis provides a determinntion that the proposed changes to Technical Specifications does not involve any significant hazards consideration as defined in 10CFR50.92.
r 1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Because no aspects of the STPECS organization that are important to safety are removed or diminished, the proposed amendment, will not involve a significant increase in the probability or consequences of any accident previously evaluated.
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. Attachment 3 Page 2 of 2 ST-HL-AE-3216 2 .- The proposed changes do not create the possibility of a new or different kind of accident from-any previously ovaluated. The~ proposed amendment is administrative in nature and does not involve any changes to plant design or ,
configuration. Therefore, the proposed changes will not j create the possibility of a new or different kind of accident. ,
l
- 3. The proposed changes do not involve a significant i reduction in the margin of safety. The proposed changes l do not remove or diminish any elements of the nuclear organization that are essential:to the safe operation of 1 STPEGS. The proposed changes do not involve any changes !
to plant operating systems or associated' safety analyses.
Therefore, the proposed changes do not involve a significant reduction in the margin of safety.
Conclusi2D The commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists.
This guidance includes examples (51FR7750) of the type of amendments that are considered not likely to involve significant hazards considerations.- The i changes proposed are cimilar to the examples of administrative changes identified in $1FR7750.
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ATTACHMENT 4 .
PROPOSED TECHNICAL SPECIFICATION 6.5.2.2 1 '
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ADMINISTRATIVE C01010L5 b
- 4 d Il h nm Ckogtetawa. V mcf %t l ece.st Seh R p COMPOSIT10N_ 3.p pggg 6.5.2.2 The NSRB shall be composed of@th; fcilwing, e~f ather :::b:r; si.11
,-be appointed in writing by the Group _Vice President, Nuclear
.Chai ~er Gen re! ".; rieger, NSES
".; be r: Cer.:r:1 ".:n:g:r, Seeth Texn Prej=t ":=;;:nr.t-
"dc r; Vice Pre 3ideni, Huclear Fioni Oper;ti = - '
";...Le i . C;r.crei "ei..wer, huciear assurance
"::b:r- ceneral u.a nger, South Texn Drej=t Op;retier,s %pp;rt-ALTERNATES 6.5 2.3 All alternate _ members shall be appointed in writing by the Group, Vice President-Huclear to sevve on a temporary basis;, however, no more than two alternates shall participate as voting rrembers in NSRB activities at any one time.
i CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to provide expert advice to the NSRB.
MEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.
l l QUORUM L- 6.5.2.6 The quorum of the NSRB necessary for the performance of the NSRB l review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least a majority of NSRB members l
! including alternates. No more than a minority of the quorum shall have line responsibility for_ operation of the unit.
L REVIEW 6.5.2.7 The NSRB shall be responsible for the review of:
L a. The safety evaluations for: (1) changes to procedures, equipment, l or systems; and (2) tests or experiments completed under the provision l of 10 CFR 50,59, to verify that such actions did not' constitute an unreviewed safety question;
- b. Propcsed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; 1 l
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SOUTH TEXAS - UNITS 1 & 2 6-10 Uni.t 1 - Amendment No. 4 1
1