View source for ST-HL-AE-5675, Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431

{{Adams
| number = ML20151L293
| issue date = 07/22/1997
| title = Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431
| author name = Groth J
| author affiliation = HOUSTON LIGHTING &amp; POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000498, 05000499
| license number = 
| contact person = 
| case reference number = RTR-NUREG-1431
| document report number = ST-HL-AE-5675, NUDOCS 9708060311
| package number = ML20151L299
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 37
| project = 
| stage = Supplement
}}

=Text=
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The Light c o m p a n&y Pe     s uth Texas Project Electric Generating                             stationTexas 77483 P.O. Box 289 Wadsworth, July 22,1997 ST-HL-AE-5675 File No.: G20.01, G20.02 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington,DC 20555 South Texas Project
* Units 1 and 2 Docket Nos. STN 50-498, STN 50-499                                             l Supplement I to Proposed License Amendment to Convert                                     l the South Texas Project Technical Specifications to the Imnroved Standard Technical Specifications Format

==References:==
: 1)      Letter from J. F. Groth to the U.S. Nuclear Regulatory Commission dated June 4,1996," Proposed License Amendment to Convert the South Texas Project Technical Specifications to the Improved Standard Technical Specifications Format"(ST-HL-AE-5390) i The South Texas Project submits the attached supplement to our original proposal                      !
(Reference 1) to amend its Operating Licenses NPF-76, Unit 1, and NPF-80, Unit 2, to convert                  ,
the South Texas Project Technical Specifications to the format of the Improved Standard                       l Technical Specifications as described in NUREG 1431, Standard Technical Specifications, Westinghouse Plants, Revision 1. This supplement is in response to the Request for Additional Information Made by the Nuclear Regulatory Commission on November 27,1996.
Supplement I to the proposed South Texas Project Improved Technical Specifications and Bases are attached. Accompanying the Technical Specifications and Bases are the annotated Current Technical Specifications, a description of changes, and the No Significant Hazards Considerations Determinations and Environmental Determinations for *.he changes. Additional informatien is provided that describes the differences between the South Texas Project Improved Technical Specifications and NUREG 1431 and provides assistance for the Nuclear Regulatory Commission staff in performing the re;iew. To assist your review of this supplement to improved Technical Specifications, each section has a sumraary sheet which describes the changes which have been made from our original submittal, a description of "beyond scope" items and a disposition of proposed generic changes.
usepaw cyu v>L, Project Manager on Behalf of the Participants in the south Texas Project          ,
9700060311 970722 ADOCK 0500 4 8
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I Houston Lighting & Power Company                                                ST-HL-AE-5675 South Texas Project Electric Generating Station                                 File No.:    G20.01, G20.02 Page 2 l
The Standard Improved Technical Specifications were written for standard plants with two trains of Engineered Safety Feature equipment. Since the South Texas Project has three trains of Engineered Safety Features, it is necessary for the South Texas Project Improved Technical Specifications to deviate from the Standard Improved Technical Specifications to reflect these features. The South Texas Project retains a high degree of redundancy, which is substantially greater than for a two-train plant during similar conditions. Unlike a two-train plant, the South Texas Project does not experience a complete loss of safety function when two of three trains of an Engineered Safety Feature function are inoperable. Thus it is appropriate for the South Texas Project to have extended allowed outage times when one of three trains is inoperable and a recsonable allowed outage time for conditions where two of three trains are inoperable.
Generally, the conversion of a two train Standard Improved Technical Specifications to      l Improved Technical Specifications suitable for a three train plant involves application of the three concepts described below. These concepts are generally applied throughout the South Texas Improved Technical Specircations submittal with some adjustment for specific system designs and redundancies. In each case, the deterministic conclusion has been tested with the
  . Probabilistic Safety Assessment to account for integrated effects and to ensure there is appropriate probabilistic justification.
The concepts used are:
: 1. Two train specifications have action statements that cover the progression from all trains available to no trains available. To convert from two train specifications to three train specifications, it is necessary to add action statements to cover the progression from three trains available to no trains available.
: 2.      The three train plant has substantially more capability to mitigate design basis events (including single failures) with one train out of service than a two train plant with one train out of service (i.e., no single failure mitigation capability).
The allowed outage times associated with the loss of one train are increased based on this additional capability.
: 3.      The three-train plant has capability to mitigate most design basis events without a i
single failure if two trains are out of service where the two-train plant has no capability with two trains out of service. This additional capability warrants provision of short allowed outage times in lieu of immediate shutdown requirements. Consequently, allowed outage times are provided for two trains out ofservice.
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Houston Lighting & Power Company South Texas Project Electric Generating Station ST-IIL-AE-5675 File No.: G20.01,                  l G20.02              l Page 3                             l In addition to the supplement to the proposed South Texas Project Improved Technical Specifications and Bases, the following items are provided to assist you in your review:
: l.         A Relocation Matrix describing where information relocated from the technical specifications was placed (Less Restrictive - Moving Details to Relocated l
Licensee Controlled Documents)(Attachment 3);                                              !
)                2.         A list of pending changes to the South Texas Project Technical Specifications l
 ;                          (Attachment 4).                                                                            .
The South Texas Project requests one year from the time of Nuclear Regulatory Commission approval for the time to implement the new Technical Specifications. This time is required to allow the station to prepare the procedure revisions and other administrative tasks necessary for the efTective implementation of the Improved Technical Specifications.                               !
4 South Texas Project has reviewed the attached proposed amendment pursuant to 10 CFR 50.92 and detennined that it does not involve a significant hazards consideration. In addition,
,   South Texas Project has determined that the proposed amendment satisfies the criteria of 10 CFR 51.22(c)(9) for categorical exclusion from the requirement for an environmental assessment.
l 4
As described in Unit 1 Licensee Event Report 97-006, dated June 6,1997, the                            i surveillance criteria in the Technical Specifications are being reviewed to confirm that                           l l   instrument uncertainty has been appropriately considered. While it is not expected, the results of l
this review may change some of the Improved Technical Specifications surveillance criteria                         i values. As stated in the Licensee Event Report, this action is expected to be completed by November 1997. This review should be substantially completed before that time to ensure that
{   there are no impacts on the Improved Technical Specifications.
Following resolution of any remaining Nuclear Regulatory Commission comments, the South Texas Project will submit, if necessary, a certified Proof and Review version of the Improved Technical Specifications targeted to support Nuclear Regulatory Commission approval                       i of the proposed amendment by the end of 1997.
In order to address new Surveillance Requirements imposed by the Technical Specifications approved and issued as a result of this License Amendment Request, the following license condition is proposed:
                "For Surveillance Requirements not previously performed by existing Surveillance Requirements or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. [ ] for the South Texas Project."
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l Houston Lighting & Power Company                                                 ST-IIL-AE-5675 South Texas Project Electric Generating Station                                  File No.: G20.01, y                                                                                                      G20.02 Page 4 The required aflidavit is included as Attachment I to this letter. The South Texas Project Plant Operations Review Committee and Nuclear Safety Review Board have reviewed and approved the proposed South Texas Project Improved Technical Specifications.
In accordance with 10 CFR 50.91(b), the South Texas Project is providing the State of Texas with a copy of this proposed amendment.
If you have any questions concerning this matter, please call Mr. M. A. McBumett at (512) 972-7206 or myself e.t (512) 972-8664 W
J. F. roth Vice President, Nuclear Generation JMP/
Attachments:
: 1.        Affidavit
: 2.        Proposed South Texas Project Improved Technical Specifications Submittal Packages, each consisting of:
A.         Proposed South Texas Project Improved Technical Specifications and Bases B.         Annotated Current Technical Specifications and Description of Changes C.         No Significant Hazards Considerations Determinations and Environmental Determinations D.         Deviations from NUREG 1431 and Justifications
: 3.         Relocation Matrix (Less Restrictive - Moving Details to Relocated Licensee Controlled Documents)
: 4.         Pending Changes to the South Texas Project Technical Specifications 1
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Houston Lighting & Power Company                                ST-HL-AE-5675 South Texas Project Electric Generating Station                 File No.:G20.02.01 Page 5 Ellis W. Merschoff                                      Rufus S Scott Regional Administrator, Region IV                       Associate General Counsel U. S. Nuclear Regulatory Commission                     Houston Lighting & Power Company 611 Ryan Plaza Drive, Suite 400                          P. O. Box 61067 Arling:on, TX 76011-8064                                 Houston, TX 77208 Thomas W. Alexion                                         Institute of Nuclear Power Project Manager, Mail Code 13H3                           Operations - Records Center U. S. Nuclear Regulatory Commission                      700 Galleria Parkway Washington, DC 20555-0001                                Atlanta, GA 30339-5957 David P. Loveless                                        Dr. Bertram Wolfe Sr. Resident Inspector                                    15453 Via Vaquero c/o U. S. Nuclear Regulatory Comm.                        Monte Sereno, CA 95030 P. O. Box 910 Bay City, TX 77404-0910
* Richard A. Ratliff Bureau of Radiation Control J. R. Newman, Esquire                                Texas Department of Health Morgan, Lewis & Bockius                               1100 West 49th Street 1800 M Street, N.W.                               Austin, TX 78756-3189 Washington, DC 20036-5869 J. R. Egan, Esquire M. T. Hardt/W. C. Gunst                        Egan & Associates, P.C.
City Public Service                                   2300 N Street, N.W.
P. O. Box 1771                                       Washington, DC 20037 San Antonio, TX 78296 J. C. Lanier/M. B. Lee
* Janet Kennedy (4 Copies)
City of Austin                                         Project Manager, Mail Code 13H3 Electric Utility Department                            U. S. Nuclear Regulatory Commission 721 Barton Springs Road                                Washington, DC 20555-0001 Austin, TX 78704 Central Power and Light Company
* Donald R. Hoffman ATrN: G. E. Vaughn/C. A. Johnson                        11921 Rockville Pike, Suite 100 P. O. Box 289, Mail Code: N5012                         Rockville, MD 20852 Wadsworth, TX 77483
* Above copies distributed with Attachments I

ATTACIIMENT 1 i
AFFIDAVIT 4
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i UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION l
In the Matter of                                 )                                                    i
                                                   )                                                    l Houston Lighting & Power                         )                 Docket Nos.      50-498            !
Company, et al.,                                 )                                  50-499            i
                                                   )                                                    l South Texas Project                              )
Units 1 and 2                                    )
AFFIDAVIT                                             i i
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I, J. F. Groth, being duly sworn, hereby depose and say that I am Vice President, Nuclear Generation, of Houston Lighting & Pov :r Company; that I am duly authorized to sign and file with the Nuclear Regulatory Commission the attached supplement to License Amendment to Convert the South Texas Project Technical Specifications to the Improved Standard Technical Specifications format; that I am familiar with the content thereof; and that the matters set forth therein are true and correct to the best of my knowledge and belief.
1M     ~   M
                                                                  . F. Groth
                                                             #Vice President,                           l Nuclear Generation                      !
STATE OF TEXAS                            )
                                            )
COUNTY OF MATAGORDA                       )
Subscribed and swom to before me, a Notary Public in and for the State of Texas, thisc$dd day of Odu                         ,1997.
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l ATTACHMENT 1                                       i L              Proposed South Texas Project Improved Technical Specifications Submittal Pachges           ,
!                A.            Proposed South Texas Project Improved Technical Specifications and Bases   !
!                B.            Annotated Current Technical Specifications and Description of Changes      :
,                C.            No Significant Hazards Considerations Determinations and Environmental     ;
L Determinations D.
Deviations from NUREG 1431 and Justifications l                                                                                                         !
l                                                                                                         !
Chapter 1.0            Use and Application Chapter 2.0            Safety Limits                                '
Section 3.0            LCO and SR Applicability                     i Section 3.1            Reactivity Control Systems                   i Section 3.2            Power Distribution Limits Section 3.3            Instrumentation
                                                                                                          )
Section 3.4            Reactor Coolant System Section 3.5            Emergency Core Cooling Systems Section 3.6            Containment Systems Section 3,7            Plant Systems Section 3.8            Electrical Power Systems     -
Section 3.9            Refueling Operations Chapter 4.0            Design Features Chapter 5.0            Administrative Controls i
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Attachment 2 ST-HL-AE-5675 Page 1 of 2 ITS SUPPLEMENT REVIEW INFORMATION Backcround The Improved Technical Specifications original submittal is being revised and supplemented based on guidance provided by the Nuclear Regulatory Commission. General guidance includes:
: 1. Removing changes that can not be supported by current licensing basis (i.e., generic industry changes) and
: 2. Providing additional information in the Discussion of Changes to more thoroughly describe the revisions to the current technical specifications.
Supolement Development and Methodology The Improved Technical Specifications submittal consists of the following elements:
: 1. Improved Technical Specifications These are the proposed Technical Specifications developed by capturing the Current Technical Specifications (current design bases) and the plant specific three trair, considerations in NUREG - 1431 format.
: 2. Improved Technical Specifications Bases The bases provide additional information to assist users in implemen'ing the specifications. They include a BACKGROUND section that provides plant specific system design and technical information; APPLICABLE SAFETY ANALYSIS section to provide a summary of why systems or limits were designed or established; and then additional detail on each element of the specification itself.
: 3. CTS Markup and Discussion of Change                                                         l l
The Current Technical Specifications markup is an administrative tool to show how        I the Current Technical Specifications was changed. This section of the submittal includes extensive detail and is actually a pencil markup showing the road map from the Current Technical Specifications to the Improved Technical Specifications Each Current Technical Specifications change is marked with an A (administrative change),
M (more restrictive change), L (less restrictive change). or LA (less restrictive change due to relocation of a requirement outside the technical specifications) followed by a   l sequential number. Each of these changes are then discussed in detail in the             l Discussion of Changes for that change. The Discussion of Changes immediately follow the Current Technical Specifications Markup and are the major emphasis of this supplement.                                                                         !
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Attachment 2 ST-HL-AE-5675 Page 2 of 2
: 4. No Significant Hazards Considerations i
These are evaluations to review any significant hazard that may result from making   '
the changes to the Current Technical Specifications. This review satisfies the       ;
requirement of10 CFR 50.92.
j
: 5. NUREG Markup (Specifications and Bases) and Justification for Deviations               '
This is a pencil markup of NUREG-1431 to show how South Texas Project is             ,
deviating from the standard and associated justifications as to why the deviation is acceptable.
[
Each of these elements are changed as necessary to implement the Nuclear Regulatory       ;
' Commission guidance. Each change is made to allow a quick review of only those           '
elements that have changed. For Improved Technical Specifications non-markup
{
elements, changes are provided ir a strike through (e.g., strike th=;;h) and underline     '
format (e.g., underline) format. The strike through shows deletions from the submittal and underline shows additions to the submittal.
For the markup elements of the Improved Technical Specifications submittal, changes are   i shown with bold markings and revision bars.
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ATTACHMENT 3                            ,
RELOCATION MATRIX (LESS RESTRICTIVE - MOVING DETAILS TO RELOCATED LICENSEE CONTROLLED DOCUMENTS) l
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ATTACIIMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTIIF t LICENSEE CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                         CONTROL DOCg1ENT IMPROVED TECHNICAL SPECIFICATION SECTION: 1.0 USE AND APPLICATION LA.1     The definitions for GASEOUS WASTE                      Offsite Dose     10 CFR 50.59 PROCESSING SYSTEM, MEMBERS OF THE                     Calculation      and 71 PUBLIC, OFFStTE DOSE CALCULATION                      Manual MANUAL, PURGE-PURGING, REPORTABLE EVENT, SITE BOUNDARY, SOURCE CHECK, UNRESTRICTED AREA, and VENTING.
LA.2      The definition for PROCESS CONTROL                    Updated Final    10 CFR 20, PROGRAM (PCP) relating to the same program            Safety           61, and 71 required by 10 CFR 20,61, and 71.                     Analysis Report LA.3      Reactivity condition limitation for REFUELING         Core             10 CFR 50.59 MODE.                                                 Operating Limits Report LA.4       Allowar.ce provided in definition of Quadrant Power   Surveillance     NA             i Tilt Ra:io to use 3 excore detectors to compute        Requirements average with one excore detector inoperable.          Improved Technical                        l Specification Limiting Condition for Operation 3.2.4 IMPROVED TECHNICAL SPECIFICATION SECTION: 2.0 REACTIVITY CONTROL SYSTEMS LA.1       Functional Unit 12 (Reactor Coolant Flow-Low)         Bases            10 CFR 50.59 Trip setpoint and Allowable Value footnote (loop design flow = 95,400 gallons per minute).
l LA.2     Notification and reporting to the Nuclear Regulatory   Procedures       10 CFR, 50.72   l Commission when safety limit violated.                                 and 73 l
South Texas Units I and 2            Page ! of 24                                     July 22,1997 1
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ATTACIIMENT 3 CURRENT TECilNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                      CONTROL DOCgENT IMPROVED TECIINICAL SPECIFICATION SECTION: 3.1 REACTIVITY CONTROL SYSTEMS LA.1      The Actions providing instructions on restoring       Bases         10 CFR 50.59
,               Shutdown margin with specific values of boron flow rate and boron concentration.
LA.2      Factors to be considered when determining             Bases         10 CFR 50.59 Shutdown margin.
LA.3      Specific values for Shutdown margin.                  Core          10 CFR 50.59 Operating
;                                                                     Limits Report LA.4      Limits of position for shutdown banks.                Core          10 CFR 50.59 Operating Limits Report 4
LA.5      Detailed information on rod inoperability as a result Bases         10 CFR 50.59 of being untrippable.                                                                   l 1
LA.6      List of accident analyses requiring reevaluation. Updated Final 10 CFR 50.59 Safety i                                                                     Analysis Report LA.7      Requirement to verify rod drop times for any rods     Procedures    Plant following maintenance or modification.                              Procedure
:                                                                                  Change Process LA.8      3.1.3.2 Limiting Condition for Operation contains     Bases         10 CFR 50.59 descriptive information more appropriate for Bases.
R.1      The specific requirements for control rod and         Technical     10 CFR 50.59 control banks positions during Special Test           Requirements Exceptions in MODES 3,4, and 5.                       Manual South Texas Units 1 and 2                Page 2 of 24                              July 22,1997

ATTACIIMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                             CONTROL DOCgENT IMPROVED TECIINICAL SPECIFICATION SECTION: 3.2 POWER DISTRIBUTION LIMITS                                                 ,
LA.1     Formulas for determining the values of Fq (Z), P,           Bases           10 CFR 50.59 and K(Z) are not required to support limit of FqZ.
1 LA.2     Requirements regarding the measured value of Fxy.           Bases           10 CFR 50.59 for determining F nZ to be increased 3% to account for manufacturing tolerances and 5% for measurement uncertainties.
LA.3     Requirements for the Fxy limits for various core            Bases           10 CFR 50.59 planes and core regions when determining Fq Z.                                                 :
LA.4     The requirement of measured value of Fq Z for other         Bases           10 CFR 50.59       !
than Fxy determination < sd requires value of F Z n
to be increased by 3% t,      count for manufacturing tolerances and 5% for measurement uncertainties.
LA.5     Equations showing the relationships of FNg , pRR yg,        Core            10 CFR 50.59 and PFui.                                                   Operating Limits Report LA.6     Descriptive information for how the requirement is          Bases           10 CFR 50.59 to be performed.
I,A.7    Provides information that the measured value of             Bases           10 CFR 50.59 N
Fg    does not include an allowance for measurement uncertainty.
South Texas Units I and 2              Page 3 of 24                                      July 22,1997

ATTACHMENT 3 CURRENT TECIINICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                       CONTROL DOCQMENT IMPROVED TECHNICAL SPECIFICATION SECTION: 3.3 INSTRUMENTATION LA.2      The statement in Note regarding detector plateaus.      Bases         10 CFR 50.59 LA.3      Notes to the Manual Reactor Trip Trip Actuating         Bases         10 CFR 50.59 Device Operational Test, Reactor Trip Breaker Trip Actuating Device Operational Test, and Reactor Trip Bypass Breaker Trip Actuating Device Operational Test.
LA.4      Wording related to RESPONSE TIME TESTING.               Bases         10 CFR 50.59 LA.5      Changes in equation variable definitions of             Updated Final 10 CFR 50.59 Overtemperature AT and Overpower AT result in           Safety moving specific definitions.                            Analysis Report LA.6      Specific information about Reactor Trip Switchgear      Plant         Plant Instrumentation trip setpoints.                         Procedures    Procedure Change Process LA.8      Specific requirement in Note detailing how to ensure    Plant         Plant permissives P-6 and P-10 are in required state.         Procedures    Procedure Change Process LA.10      All the functions initiated by a safety injection       Bases         10 CFR 50.59 signal (e.g., R: actor Trip, Feedwater Isolation, etc.)
l LA.11      Descriptive information that pressure is compensated    Bases         10 CFR 50.59    {
for Compensated Steam Line Pressure--Low.
LA.13      The descriptive information that there is one channel   Bases         10 CFR 50.59 per loop in regards to T,.,-Low for feedwater isolation.
South Texas Units 1 and 2               Page 4 of 24                                 July 22,1997

I ATTAC11ME?
CURRENT TECilNICAL SPECIFICATION REQUIREN CONTROLLED DOC CURRENT TECllNICAL RE                          SP DOC                          ISSUE RELOCATED                                                               CONTROLLI.
o LA.15      Denriptive information contained in At                    DOC                                           .---.
Feedwater Steam Generator Level-Low                   '                               ISSUE RELOCAT Loss of Power state that Auxiliary Feed                  LA.23 Generator Level starts the motor and stt                              List of the total
                                                                                                          ?       """"
pumps and the Loss of Offsite Power is                                shutdown instrumentation.
motor driven pumps only.
LA.16      Descriptive Note which states automati                  LA.24 to containment sump is accomplished i                                Listing of the Readout Locat using the corresponding Refueling Wa g                Location and Controls L Tank level transmitter.                                             shutdown instrumentation L
LA.17      Turbine Trip and Feedwater Isolation                  LA.25 a gh liigh and Auxi Generator Steam Generator Level - Low L w d                 f                 Allowable Values for t the trip setpoi s an               e value of   the containment ve instrumentation.
narrow rang           ument span."
LA.26 LA.18                                                                                                                   _
The " Total No. Of Channels" colum Acciden         onitoring Instrumentatio' Modification by footnote for Containment Actuation       Logic and Actuati      Ve function is actuated by e LA.19      Information located in the foot not' actuation this function. train B; Actuati Monitoring                   don" for th           LA.27 Water Leve Instruments describin:                               Manual initiation requirem sensors in p                    ion of rc that has 1        OPERABLE for chi              _
three channels ofini per train.                              ao 1
OPERABLE.                                       - LA.28                                                      j AAllowable                 Values          forH t
LA.22     Specific information requiring Ch                               he Control Room              Envelope   entis ing " sample gi                     re ir Conditioning system actu vo                                                                                                          m e percent hydrogen, balane                        e quired during performance o Ansure trip setpoint                 is conse
                                                          .                 llowable Value.
                                                          ! LA.29      M thr  anual initiation requiremen ee channels ofinitiation per train.
a onin    6 South Texas Units I and 2 Page5 c South Texas Units I and 2 Page 6 of' 24

ATTACIIMENT 3                                                l CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                      ISSUE RELOCATED                                            CONTROL DOCg1ENT LA.15      Descriptive information contained in Auxiliary          Bases            10 CFR 50.59 i              Feedwater Steam Generator Level-Low Low and Loss of Power state that Auxiliary Feedwater Steam Generator Level starts the motor and steam driven
 ,             pumps and the Loss of Offsite Power is for the motor driven pumps only.
;    LA.16      Descriptive Note which states automatic switchover      Bases            10 CFR 50.59
:              to containment sump is accomplished for each train using the corresponding Refueling Water Storage Tank level transmitter.
4 LA.17     Turbine Trip and Feedwater Isolation Steam               Bases            10 CFR 50.59   .
,              Generator Level-High High and Auxiliary Feedwater i
Steam Generator Le'cel - Low Low descriptions that the trip setpoints and allowable values are "of narrow range instrument span."
e LA.18     The " Total No. Of Channels" column for Post             Updated Final    10 CFR 50.59 Accident Monitoring Instrumentation.                     Safety Analysis
,                                                                       Report LA.19     Information located in the foot note for " Accident      Bases            10 CFR 50.59 Monitoring Instrumentation" for the Reactor Vessel Water Level Instruments describing number of sensors in probe and location of required number that has to be OPERABLE for channel to be i              OPERABLE.
LA.22     Specific information requiring Channel Calibration       Plant            Plant to be performed using " sample gas containing ten        Procedures       Procedure j              volume percent hydrogen, balance nitrogen."                               Change
,                                                                                        Process j
l i  South Texas Unitr I and 2             Page 5 of 24                                      July 22,1997

_ _ _ - =            _ . . -         - - - - . - .. .                             . .
ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                            ISSUE RELOCATED                             DOCgENT        CONTROL LA.23      List of the total number of channels for remote                  Updated Final 10 CFR 50.59 shutdown instrumentation.                                        Safety i                                                                               Analysis Report i                                                                                                               l LA.24      Listing of the Readout Location, Transfer Switch                 Plant         Plant
:              Location and Controls Location for remote                        Procedures    Procedure         l shutdown instrumentation                                                       Change Process l
LA.25      Allowable Values for the radiation monitor channels              Plant         Plant             I of the containment ventilation isolation                         Procedures    Procedure instrumentation.                                                               Change Process LA.26      Modification by footnote regarding instrumentation               Bases         10 CFR 50.59      ;
for Containment Ventilation Isolation Automatic                                                  l Actuation Logic and Actuation Relays stating the function is actuated by either actuation train A or actuation train B; Actuation train C is not used by                                              l this function.
I LA.27      Manual initiation requirements specifying that the               Bases         10 CFR 50.59 three channels of initiation instrumentation are one per train.                                                                                       '
LA.28      Allowable Values for radiation monitors channels of              Plant         Plant the Control Room Envelope Heating Ventilation and                Procedures    Procedure Air Conditioning system actuation instrumentation,                             Change required during performance of surveillance test to                            Process ensure trip setpoint is conservative with respect to Allowable Value.
LA.29      Manual initiation requirements specifying that the               Bases         10 CFR 50.59 three channels of initiation instrumentation are one per train.
South Texas Units 1 and 2                Page 6 of 24                                         July 22,1997 i

a ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED 'IO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                           CONTROL DOCgENT
:           LA.30     Allowable Values for radiation monitors channels of        Plant        Plant the Fuel Handling Building Heating Ventilation and         Procedures   Procedure Air Conditioning actuation instrumentation, required                    Change during performance of surveillance test to ensure                       Process
: l.                    trip setpoint is conservative with respect to
;                     Allowable Value.
1 l           LA.33     Footnote details for extended range neutron flux           Plant        Plant                ;
;                     monitor quarterly Analog Channel Operational Test          Procedures   Procedure            I l                     requirements for operability verification by check of                   Change memory devices, input accuracies, boron dilution                        Process alarm setpoints, output values and software j                     functions.
j           LA.34     Action 30 allowing movement ofloads over the               STP Heavy    Plant 4
spent fuel pool to continue provided the Fuel              Loads        Procedure l                     Ilandling Building Heating Ventilation and Air             Program      Change j                     Conditioning is placed in operation.                                    Process i            R.1      The requirements on Movable Incore Detectors.              Technical    10 CFR 50.59 Requirements Manual R.2      The requirements on Seismic Instrumentation.               Technical    10 CFR 50.59 Requirements Manual
;            R.3      The requirements on Meteorological Instrumentation.        Technical    10 CFR 50.59
;                                                                                Requirements
,                                                                                Manual
;            R.5      The requirements on Explosive Gas Monitoring               Technical    10 CFR 50.59
;                     Instrumentation.                                           Requirements
,                                                                                Manual i
j            R.6      The requirements on Turbine Overspeed Protection.          Technical    10 CFR 50.59 Requirements Manual 4
South Texas Units 1 and 2                Page 7 of 24                                      July 22,1997

__      _        _ _        _ _.       .   ~       _    .
ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS 4
DOC                       ISSUE RELOCATED                                        CONTROL DOCg1ENT IMPROVED TECHNICAL SPECIFICATION SECTION: 3.4 REACTOR COOLANT                                l SYSTEM (RCS)
LA.1      Footnote to Reactor Coolant System total flow rate      Bases         10 CFR 50.59 limit describing the inclusion of a flow measurement uncertainty in the flow rate limit.
.+
l     LA.2      Limits, including figures, regarding Reactor Coolant    Pressure and  Improved       l
,               System pressure, temperature, and heatup and            Temperature   Technical      j cooldown rates                                          Limits Report Specification 5.6.6          i LA.3      The action requirement to " perform an engineering      Bases         10 CFR 50.59 evaluation to determine the effects of the out-of-i limit condition on the structural integrity of the                                   !
,               Reactor Coolant System."
s LA.4      The requirement to remove and evaluate the              Plant         10 CFR 50 properties of the reactor vessel material surveillance  Procedures    Appendix H specimens as required by 10 CFR Part 50, Appendix H.
l LA.5      The detail of what constitutes an OPERABLE              Bases         10 CFR 50.59 Reactor Coolant System loop.
t I
LA.6      Details of what constitutes an OPERABLE                 Bases         10 CFR 50.59 subsystem including the status ofindividual components and their support requirements.                                           .
LA.7      Information related to the Containment Atmosphere       Plant         Plant Radioactivity-High Function of the Radiation            Procedures    Procedure Monitoring Instrumentation Information related                        Change
,                                                                                     Process LA.8      The " circulating reactor coolant" portion of the       Bases         10 CFR 50.59
.;              surveillance requirements which assure that a loop is in operation and circulating reactor coolant.
s South Texas Units 1 and 2               Page 8 of 24                                 July 22,1997 1

ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                       CONTROL DOCgENT LA.9      Requirement for potential dilution flow isolation       Bases         10 CFR 50.59 valves to be " closed and secured by mechanical stops or removal of air or electrical power," being changed to " closed and secured." Remaining portions are relocated.                                                              l LA.10      Design detail describing pressurizer heaters capable    Bases         10 CFR 50.59 of being powered from Engineered Safety Features power supplies.
LA.11      Details of how testing of the pressurizer heaters is to Bases         10 CFR 50.59 be done.
LA.12      The lift settings applicable to the Power Operated      Pressure and  10 CFR 50.59    l Relief Valves and the Residual Heat Removal             Temperature discharge relief valves.                                Limits Report                 l LA.13      Footnote to Actions B and C which states the            Bases         10 CFR 50.59 operation of systems or components would result in an Reactor Coolant System temperature increase will be administratively controlled.                                                       :
1 L.A.14     Description of how inoperable pumps are to be           Bases         10 CFR 50.59 verified inoperable ofinjecting to the Reactor Coolant System.
LA.16      List of Reactor Coolant System Pressure isolation       Updated Final 10 CFR 50.59 valves                                                  Safety Analysis Report LA.17      Requirement to perform Pressure isolation valve         Plant         Plant leakage testing prior to returning a valve to service   Procedures    Procedure       i following maintenance.                                                Change          !
Process i
South Texas Units 1 and 2              Page 9 of 24                                  July 22.1997

ATTACHMENT 3                                                    i CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTilER LICENSEE                                    l CONTROLLED DOCUMENTS I
DOC                                                                                                         !
ISSUE RELOCATED                      DOCg1ENT        CONTROL             l LA.18      Specif'ic section and paragraph of the American               Plant          Plant Society of Mechanical Engineers' code specifying              Procedures     Procedure frequency of leakage testing of the Reactor Coolant                          Change               ,
System Pressure isolation valve.                                             Process l
I LA.19      Requirements associated with determining Dose                 Bases          10 CFR 50.59 Equivale it I-131 and gross specific activity of reactor coolant with details of types of testing to be performed.
LA.21      Requirements to ensure leak test requirements of              Inservice      10 CFR Pressure isolation valves are met.                            Testing        50.55a Program R.1      The requirements on reactor coolant CIIEMISTRY.               Technical      10 CFR 50.59 Requirements Manual R.2      The Pressurizer heatup and cooldown rate limits.              Technical      10 CFR 50.59 Requirements Manual R.4      The requirements on Reactor Vessel Head Vent                  Technical      10 CFR 50.59 System.                                                       Requirements Manual South Texas Units I and 2                   Page 10 of 24                                   July 22,1997      ,

ATTACIIMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                         ISSUE RELOCATED                                  CONTROL DOCg1ENT IMPROVED TECHNICAL SPECIFICATION SECTION: 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
LA.1      Detail stipulating how to assure that accumulator     Bases      10 CFR 50.59 borated water volume and nitrogen cover pressure is within limits (i.e., "by the absence of alarms").
LA.4      The detail of what individual subsystems constitutes  Bases      10 CFR 50.59 an OPERABLE Emergency Core Cooling System / Residual Heat Removal subsystem.
LA.5      The details of the method used to assure that the     Bases      10 CFR 50.59 Emergency Core Cooling System piping is full of water.
LA.6      Details of pump pressure limits for inservice testing Procedures 10 CFR of High Head Safety Injection, Low Head Safety                   50.55a Injection and Residual Heat Removal pumps. The Inservice Testing program is controlled by 10 CFR 50.55a.
LA.7      Details of steps required to isolate High Head Safety Bases      10 CFR 50.59 Injection pump from Reactor Coolant System provided in Note.
LA.8      Requirement in Action b to provide a Special Report              10 CFR 50.73 in event the Emergency Core Cooling System is actuated and injects water into Reactor Coolant System is deleted; adequately captured by requiring report in the event of Emergency Core Cooling System actuation within 30 days.
I l
South Texas Units 1 and 2               Page 1I of 24                           July 22,1997 l

ATTACHMENT 3                                                  l CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS                                              I l
DOC                   ISSUE RELOCATED                                         CONTROL DOCg1ENT IMPROVED TECHNICAL SPECIFICATION SECTION: 3.6 CONTAINMENT SYSTEMS LA.1  The sentence regarding the exception provided in          Bases        10 CFR 50.59 3.6.3.
LA.2  Detail regarding meeting the leak rate testing            Containment  10 CFR 50 requirements stated in 10 CFR 50 Appendix J.              Leakage Rate Appendix J          !
Testing Program LA.3  Descriptive information regarding Tri Sodium              3ases        10 CFR 50.59 Phosphate as to the number of storage baskets, their integrity and level marks indicating volume.
LA.4  Descriptive information regarding Operability of the      Bases        10 CFR 50.59         l air locks.
LA.6  Information concerning the pneumatic seal system          Containment  10 CFR 50.59 for the personnel air lock doors.                         Leakage Rate and 10 CFR Testing      50 Appendix J Program LA.7  Specific leakage rate testing criteria for the 48" and    Bases        10 CFR 50.59 18" purge supply and exhaust valves.
LA.8  Requirement as to operability for each containment        Plant        Plant isolation valve; cycling of valves or performance of      Procedures   Procedure isolation time test prior to return to service after                   Change maintenance, repair or replacement work on valve or                    Process its associated actuator, control or power circuit.
LA.9  Descriptive material contained in 4.6.3.2, relating to    Bases        10 CFR 50.59 actuation signals.
LA.10 Descriptive information of how the average                Bases        10 CFR 50.59 containment temperature shall be the arithmetical average of a minimum of 4 Reactor Containment Fan Coolers inlet temperatures.
South Texas Units 1 and 2              Page 12 of 24                                  July 22.1997

i
  <                                                                                                   l ATTACllMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OT11ER LICENSEE CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                    CONTROL DOCg1ENT LA.11      Descriptive information regarding system             Bases        10 CFR 50.59 operability.
j     LA.12      Descriptive information regarding the current        Bases        10CRF50.59         l hydrogen recombiner surveillances.                                                   l t
LA.13      Requirement to perform a Channel Calibration on all  Plant        Plant              i
:               the hydrogen recombiner instrumentation.             Procedures   Procedure          l
,                                                                                  Change             !
Process
;     LA.14      Requirements specifying how to isolate penetrations  Bases        10 CFR 50.59
!                which contain an inoperable valve.
,     LA.15      Performance requirement of isolation valve testing   Bases        10 CFR 50.59 j                during shutdown every 18 months.
i     LA.16      Details of what constitutes an operable isolation    Bases        10 CFR 50.59
:               barrier.
i                                                                                                    i i
;          IMPROVED TECIINICAL SPECIFICATION SECTION: 3.7 PLANT SYSTEMS                               i i
a LA.1     The orifice size of each Main Steam Safety Valve. Bases        10 CFR 50.59 j      LA.2     The Lift Setting Note which requires the lift setting Bases        10 CFR 50.59 l               pressure to correspond to ambient conditions of the
;                valve at nominal operating temperature and pressure.
.      LA.3      Requirements for manual controls of the Steam        Bases        10 CFR 50.59 Generator Power Operated Relief Valves.
l
!      LA.4      Details defining type of pumps and their power       Bases        10 CFR 50.59 source.
{      L.A.5    The details related to the Auxiliary Feedwater        Plant        Plant pumps including pump discharge pressure and flow      Procedures   Procedure requirements.                                                      Change Process South Texas Units I and 2             Page 13 of 24                              July 22,1997 2
t

    . -         .                 .     . .            . = , , - . -      --     _  -   - _ .  - -        - - .
ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                           CONTROL
;                                                                            DOCgENT LA.6      The requirement for each auxiliary feedwater flow       Plant            Plant rquiating valve limiting flow to each steam             Procedures       Procedure generatt r.                                                              Change Process LA.7      Requirements for Channel Calibration on surge tank      Bases            10 CFR 50.59 level instrumentation including detail related to actions after the signal.
4 LA.8      Requirement for each Component Cooling Water            Bases            10 CFR 50.59 loop to be independent.
LA.9      Requirement for each Component Cooling Water            Bases            10 CFR 50.59 loop to be independent.
LA.ll      Requirement that the Main Feedwater Isolation           Plant            Plant Valve bypass valves and preheater bypass valves be      Procedures       Procedure demonstrated OPERABLE following maintenance,                             Change repair, or replacement work on the valve.                                Process
.         LA.12      Requirement that each Control Room Envelope             Bases            10 CFR 50.59 Heating Ventilation and Air Conditioning train be independent
;         LA.13      Specification that Control Room Envelope Heating        Plant            Plant Ventilation and Air Conditioning Operability test be    Procedures       Procedure initiated from control room and flow through High                        Change Efficiency Particulate Air filters and charcoal                          Process 4
adsorbers of the makeup and cleanup air filter units.
LA.14      Listing of the specific actions of the system after the Plant            Plant simulated initiation signal .                           Procedures       Procedure Change f                                                                                             Process l
South Texas Units 1 and 2              Page 14 of 24                                     July 22,1997

ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                      CONTROL DOCg1ENT LA.16      Verification that the control room air temperature is Plant         Plant s 763F once per 12 hours.                             Procedures    Procedure Change Process LA.17      Requirements defining composition of Fuel             Bases         10 CFR 50.59 Handling Building Heating Ventilation and Air Conditioning.
LA.18      Requirements as to where to initiate Surveillance,    Bases and     10 CFR 50.59 how to maintain proper flow, etc.                     Plant p,
Procedures Procedure Change Process LA.19      Requirement specifying the boron concentration of     Bases         10 CFR 50.59 the spent fuel pool shall be determined by chemical analysis.
LA.20      Requirements as to the Spent Fuel Pool Spen'. Fuel    Bases         10 CFR 50.59 Assembly Storage specifics.
LA.21      Specific In-Containment Storage Area Spent Fuel       Bases         10 CFR 50.59 Assembly Storage Requirements.
LA.22      Statements for Auxiliary Feedwater, Component         Bases         10 CFR 50.59 Cooling Water and Essential Cooling Water that indicate performance of the surveillance is "during shutdown".
R.1      The Steam Generator Pressurefremperature              STP Technical 10 CFR 50.59 Limitation.                                           Requirements Manual R.2      The Snubbers.                                         STP Technical 10 CFR 50.59 Requirements Manual South Texas Units I and 2             Page 15 of 24                                July 22,1997

ATTACIIMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS DOC                           ISSUE RELOCATED                                                  CONTROL DOCg1ENT R.3      The requirements on Sealed Source Contamination.                 STP Technical   10 CFR 50.59         i Requirements Manual R.4      The requirements on Area Temperature Monitoring                  STP Technical   10 CFR 50.59 Requirements Manual IMPROVED TECIINICAL SPECIFICATION SECTION: 3.8 ELECTRICAL POWER SYSTEMS 1
LA.1      Details regarding design capabilities of the electrical          Bases           10 CFR 50.59 power and associated support systems.
LA.2      Descriptions in note of required circuit capabilities            Bases           10 CFR 50.59 and application and required actions based on hypothetical conditions.
LA.3      Details regarding how diesel generators are to be                Bases           10 CFR 50.59 started during testing.
LA.4      Details requiring performance of an inspection of                Plant           10 CFR 50.59 the diesel--in accordance with manufacturer's                    Procedures instructions once per 18 month:,.
LA.5      The size of the load which must be rejected by the               Plant Design    10 CFR 50.59 Standby Diesel Generator.
LA.6      Information describing why a standby diesel                      Bases           10 CFR 50.59 generator became inoperable.
LA.7      The requirement to verify that the auto-connected                Plant Design    10 CFR 50.59 loads to each Standby Diesel Generator do not exceed the 2000 hour rating of 5935 kilowatt.
South Texas Units 1 and 2                            Page 16 of 24                                  July 22,1997

1 l                                            ATTACllMENT 3 l    CURRENT TECilNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTIIER LICENSEE
;                                       CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                   CONTROL DOCg1ENT LA.8      Requirement to verify design features of Standby      Plant      Plant Diesel Generator control circuitry and load           Procedures Procedure      l sequencer which are not required to function for the             Change         1 systems to perform their design features.                        Process        !
l LA.9      Restrictions on crane operation with loads over spent Plant      Plant fuel pool when less that the minimum required AC      Procedures Procedure electrical power sources are OPERABLE.                           Change Process 1
LA.10      Information regarding detail about specific           Bases      10 CFR 50.59 equipment that must be operable when an Standby Diesel Generator is inoperable.
LA.11      Requirement to use sodium hypochlorite solution or    Plant      Plant equivalent to clean the diesel generator fuel tank    Procedures Procedure once every ten years.                                            Change Process LA.12      Requirement to perform a pressure test on certain     Plant      Plant          !
portions of the diesel fuel oil system in accordance  Procedures Procedure with American Society of Mechanical Engineers'                   Change code.                                                            Process L.A.13     Listing of the specific unit names, battery           Bases      10 CFR 50.59 designations, and required number of battery chargers for an associated 125-volt channel.
LA.14      Definition of degradation, in terms of battery        Bases      10 CFR 50.59 capacity and specifics as to the level for performance test results by comparison with manufacturer's rating for acceptable results.
LA.15      Detailed information as to six connected cells.       Bases      10 CFR 50.59 South Texas Units I and 2             Page 17 of 24                             July 22,1997 l

l l                                            ATTACIIMENT 3 I
CURRENT TECIINICAL SPECIFICATION REQUIREMENT RELOCATED TO OTIIER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                   CONTROL DOCIg1ENT l                                                                                                l LA.16      Description of the vital Alternating Current        Bases         10 CFR 50.59 distribution panels being energized from a specific inverter powered from a speci6cally numbered                                      i l              Direct Current bus.                                                               !
LA.17      Description and clariGcation of Distribution        Bases         10 CFR 50.59 Systems-Operating.
LA.18      Unit name and battery bank from which the 125-      Plant         Plant Volt Direct Current distribution subsystems are     Procedures    Procedure energized.                                                         Change          ,
Process         I l
LA.20      Requirement that after any modiHcation which could  Plant         Plant           i affect standby diesel generator interdependence to   Procedures    Procedure       I start all standby diesels simultaneously when the                 Change plant is shut down.                                                Process        j l
LA.21     Notation that allows credit to be taken for events   Bases         10 CFR 50.59 that satisfy particular surveillances.                                             l IMPROVED TECIINICAL SPECIFICATION SECTION: 3.9 REFUELING OPERATIONS LA.1      SpeciDe boron concentration and K, requirements. Core          10 CFR 50.59 Operating Limits Report LA.2     The detail which stipulates how to restore the boron Plant         Plant concentration to within limits.                      Procedures    Procedure
!                                                                                Change Process LA.3     The detail which speciBes that boron concentration   Bases         10 CFR 50.59 be determined by chemical analysis.
LA.4     The details which identify one unborated water       Bases         10 CFR 50.59 sources valves and the methods of closing them.
South Texas Units I and 2              Page 18 of 24                             July 22,1997

l                                                  ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS
!                                                                                                                       l DOC                         ISSUE RELOCATED                                                     CONTROL DOCg1ENT LA.5     The specific detail which specifies that the Source                     Bases        10 CFR 50.59 Range Neutron Flux Monitors have continuous i             visual indication in the control room.
l j    LA.6     Specific details which allow Extended Range                             Bases        10 CFR 50.59 l             Monitors to replace Source Range Monitors.
LA.7     Specific details when an individual is available to                     Plant        Plant close a PAL door when directed after the initiation                     Procedures   Procedure l             of a Fuel Handling Accident.                                                         Change               I Process LA.9     The requirement that the two Residual Heat                              Bases        10 CFR 50.59 Removal loops be independent.
R.1     Decay Time.                                                             Technical    10 CFR 50.59 Requirements
;                                                                                     Manual i
R.2     Communications.                                                         Technical    10 CFR 50.59 Requirements Manual R.3     Refueling Machine                                                       Technical    10 CFR 50.59 Requirements Manual R.4     Crane Travel - Fuel Handling Building                                   Technical    10 CFR 50.59 Requirements l                                                                                     Manual                            j 4
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South Texas Units I and 2              Page 19 of 24                                               July 22,1997 I
i

ATTACllMENT 3 CURRENT TECliNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTilER LICENSEE CONTROLLED DOCUMENTS l
I l
DOC                        ISSUE RELOCATED                                            CONTROL DOCgENT l
l          IMPROVED TECIINICAL SPECIFICATION SECTION: 4.0 DESIGN FEATURES i
LA.1       Details of design of rod cluster control assemblies        Updated Final  10 CFR 50.59 which are not directly pertinent to the actual             Safety requirement.                                               Analysis Report LA.3       Description ofIn-Containment Storage Pool Spent            Bases          10 CFR 50.59
!                  Fuel Assembly Storage requirements.
LA.5       General site information details and substantive           Offsite Dose   10 CFR 50.59 contents of maps defining the unrestricted areas and       Calculation    & 50.71 l                  site boundary for gaseous and liquid effluent.             Manual LA.6       General description of containment configuration           Updated Final  10 CFR 50.59 and design pressure and temperature details for            Safety         & 50.71 i                  inclusion in the Design Features of the Technical          Analysis
!                  Specifications.                                            Report
!       LA.7       Description of the reactor coolant system design           Updated Final  10 CFR 50.59 pressure and temperature details for inclusion in the      Safety         & 50.71 Design Features section of the Technical                   Analysis Specifications.                                            Report LA.8       Detailed description of spent fuel storage racks and       Updated Final  10 CFR 50.59 discussion of the safety evaluation for the                Safety         & 50.71 misloading of fuel within the racks.                       Analysis Report LA.9       Design requirements for reactor coolant system and         Updated Final  10 CFR 50.59 reference to Component Cyclic and Transient Limit          Safety Program.                                                   Analysis Report l      LA.10       Restriction to prevent mixing of different types of        Updated Final  10 CFR 50.59 l                  Rod Cluster Control Assembly control material              Safety I
within a bank.                                             Analysis Report i
South Texas Units 1 and 2              Page 20 of 24                                      July 22,1997 i

l l
ATTACIIMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE I                                      CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                        CONTROL DOCg1ENT l
IMPROVED TECHNICAL SPECIFICATION SECTION: 5.0 ADMINISTRATIVE CONTROLS LA.1      The requirement to have a management directive on      Updated Final   10 CFR 50.59 the control room command function signed by the        Safety         and 50.71 Site Vice President, Nuclear and reissued on an        Analysis annual basis.                                          Report LA.2      Current Technical Specification 3/4.4.10, " Structural STP Inservice   10 CFR Integrity."                                            Inspection      50.55a Program LA.3      Note which allows the Fire Brigade composition to      Updated Final   10 CFR 50.59 be less than the minimum for a period of time not to   Safety         and 50.71 exceed 2 hours in order to accommodate unexpected      Analysis absence.                                               Report LA.7      The requirements for the Independent Safety            Updated Final   10 CFR 50.59 Engineering Group.                                     Safety         and/or 10 Analysis       CFR 50.71 Report LA.8      Requirement that retraining and replacement training   Updated Final   10 CFR 50.59 for the unit staff be maintained under the direction   Safety of the Training Manager.                               Analysis Report LA.9      Requirements for the STP onsite review committee       Updated Final    10 CFR (Plant Operations Review Committee) -- PORC.           Safety         50.59 and 10 Analysis       CFR 50.71 Report LA.10      Requirements of the STP offsite review committee       Updated Final   10 CFR 50.59 (Nuclear Safety Review Board) --NSRB.                   Safety        and 50.71 Analysis Report South Texas Units I and 2             Page 21 of 24                                   July 22,1997

ATTACHMENT 3 CURRENT TECilNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTilER LICENSEE CONTROLLED DOCUMENTS DOC                        ISSUE RELOCATED                                        CONTROL DOCpENT LA.11      The Technical Review and Control requirements as      Updated Final    10 CFR 50.59 to review of each procedure.                          Safety           and 50.71 Analysis Report                          !
LA.13      Requirements on safety limit violations.              Updated Final    10 CFR 50.59 Safety                          l Analysis                        i Report                          i LA.14      Requirements regarding the Security Plan,             Respective       10 CFR 50.59 Emergency Plan and Process Control Program.           plans / programs LA.15      Specifics on the component cyclic transient limit not Updated Final    10 CFR 50.59   i to exceed 1.0 for cumulative fatigue usage factor     Safety                          i when analyses performed according to American         Analysis                        i Society of Mechanical Engineers' Code Section III. Report LA.16      Surveillance requirements to ensure containment       Pre-Stressed     10 CFR 50.59 structural integrity,                                 Concrete Containment Tendon Surveillance Program LA.17      Details of the Inservice Inspection Program.          Plant            10 CFR controlled       50.55a(g) and Inservice        50.59 Inspection Program LA.18      Surveillance Requirement not being moved to           Ventilation      Plant Chapter 5.0 and all Frequencies for testing the       Filter Testing   Procedure ventilation filter trains.                            Program          Change Ventilation      Process Filter Test Program.         10 CFR 50.59 South Texas Units 1 and 2               Page 22 of 24                                 July 22,1997

ATTACHMENT 3                                                    5 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE                                  i CONTROLLED DOCUMENTS 1
DOC                        ISSUE RELOCATED                                            CONTROL DOCgENT l
LA.19      Requirements for Liquid Holdup Tanks, Explosive             Explosive Gas  10 CFR 50.59 Gas Mixture, and Gas Storage Tanks.                         and Storage Tank Radioactivity                      !
Monitoring Program LA.21      Specifics which apply to each Nuclear Regulatory            Core           10 CFR 50.59 Commission reviewed and approved analytical                 Operating                          ;
method used to determine the Core Operating Limits          Limits Report Report.                                                                                        l l
                                                                                                            )
LA.22      Requirements for Record Retention                           Updated Final  10 CFR 50.59        l Safety Analysis Report LA.23      Requirements for Startup Report following receipt of        Updated Final  10 CFR 50.59 an operating license; installation of a fuel of             Safety different design or manufactured by different fuel          Analysis supplier; modifications that alter the nuclear, thermal     Report or hydraulic perfc mance of unit; and amendments            Chapter 14 to the license involving planned increase in power operation.
LA.24      Requirements for Radiological Environmental                 Offsite Dose   10 CFR 50.59 Monitoring Program.                                         Calculation    and 71 Manual LA.25      Requirements of In-Plant Radiation Monitoring.              Updated Final  10 CFR 50.59 Safety         and 50.71 Analysis                           i Report Chapter 11                         :
l South Texas Units 1 and 2               .Page 23 of 24                                    July 22,1997

I ATTACHMENT 3 CURRENT TECHNICAL SPECIFICATION REQUIREMENT RELOCATED TO OTHER LICENSEE I                                      CONTROLLED DOCUMENTS DOC                       ISSUE RELOCATED                                                CONTROL DOCg1ENT LA.26     Program requirements for Accident Monitoring            Updated Final         10 CFR 50.59 Instrumentation.                                        Safety Analysis l                                                                      Report 1
l LA.27     Details of the Inservice Testing Program.               Plant                 10 CFR
;                                                                      controlled            50.54(f) and l
Inservice             50.59 Testing Program LA.28     Requirements of submittal of an annual report to        Plant                 Plant Nuclear Regulatory Commission by March 1                Procedures            Procedure            !
containing results of specific activity analyses in                           Change               j which primary coolant exceeded limits of the                                  Process              !
Reactor Coolant System Specific Activity Specification.
LA.32     Requirement that Core Operating Limite Report be        Plant                 Plant maintained available in the Control Room.               Controlled            Procedure Document              Change Matrix                Process Table Notations:
l
: 1.   " Procedures" includes plant procedures, programs, directives, and/or policies.
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South Texas Units I and 2             Page 24 of 24                                          July 22,1997 f
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ATTACHMENT 4 PENDING CIIANGES TO Tile SOUTil TEXAS PROJECT TECHNICAL SPECIFICATIONS   l l
l i
                                                                          )
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e Wrp'etorc-v4w97J675b doc                                  STI 30315545

l j                                                                                                                                     Attachment 4 j                                                                                                                                     ST-IIL-AE-5675 l
Page1of1 Proposed changes to current Technical Specifications which are currently on the docket which 3
have not been approved by the Nuclear Regulatory Commission are as follows:
i 4
I l       #             ( 'u rrent      Dewription           .
Date Submitted            I. citer #
l             .
                      'l ech
;                     sijet#                     -
3
!       l             3.4.5           Incorporate Steam Generator Tube                                           August 29,1996            ST-liL-AE-5352 l
3.4.6.2         Repair By Electrosleeving In Technical j                                     Specifications 2             4.7.3.b.3       Proposed Revision To Technical                                             July 8,1996               ST-HL-AE-5402
;                                     Specifications Clarifying Surveillance
;                                     interval For Surge Tank Level                                                                                        l j                                     instrumentation j       3             6.2.3           Removal ofIndependent Safety                                               January 28,1997           ST-IIL-AE-5547
'                                     Evaluation Group from Technical Specifications 4*            3.4.5           Steam Generator Tube Repair Using                                          January 14,1997           ST-HL-AE-5550 j                     3.4.6.2         Laser Welded Sleeves l       5*            5.3.1           Proposed Amendment of Technical                                            April 22,1997             ST-IIL-AE-5622 l                     6.9.1.6         Specifications To Allow Use of Zirlo i                                     Fuel Cladding And Limited Substitution of Zirlo Filler Rods 6             3.2.5           Proposed Amendment of Technical                                            July 16,1997              ST-11L-AE-5692 l                                     Specifications for Reactor Coolant l                                     System Flow Monitoring Due to the belief that Technical Specifications License Amendment Requests for Items #
j                            4 and # 5 will be approved imminently by the Nuclear Regulatory Commission, the South i                            Texas Project has incorporated the changes into this proposed supplement to the j                            Improved Technical Specifications.
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t \wp\nbC-mkW 9D675b doc                                                                                                            $T! 30315545 J
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