Text

Proposed Change to Radiation Monitoring Technical Specification
	ML020580493
Person / Time
Site:	South Texas
Issue date:	02/14/2002
From:	Sheppard J; South Texas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NOC-AC-01001168
	Download: ML020580493 (37)
	v • d • e

Nuclear Operating Company South Texas Piolect Electn'c GeneratinS Stab'on PC. Box 289 Wdsworth, Texas 77483 February 14, 2002 NOC-AE-01001 168 10CFR50.90 STI: 31339416 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units I and 2 Docket Nos. STN 50-498, STN 50-499 Proposed Change to Radiation Monitoring Technical Specifications STP Nuclear Operating Company (STPNOC) submits the attached proposed amendment to South Texas Project Operating Licenses NPF-76 and NPF-80.

This license amendment request proposes revising various Technical Specifications governing radiation monitoring instrumentation to eliminate the associated shutdown action requirements and relax certain other restrictions.

STPNOC requests approval of the proposed amendment by January 31, 2003. STPNOC requests 60 days for implementation of the amendment after it is approved.

The STPNOC Plant Operations Review Committee and Nuclear Safety Review Board have reviewed and concurred with the proposed change to the Technical Specifications.

In accordance with 10 CFR 50.91(b), STPNOC is notifying the State of Texas of this request for license amendment by providing a copy of this letter and its attachments.

NOC-AE-01001168 Page 2 If there are any questions regarding the proposed amendment, please contact Mr. A. W. Harrison (361) 972-7298 or me at (361) 972-8757.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on 4 1 0 dkte

?.Shep~pD Vice President Engineering & Technical Services awh/

Attachments:

1. Description of Changes and Safety Evaluation

2. Annotated Technical Specification Pages

3. Technical Specification Pages with Proposed Changes Incorporated

NOC-AE-01001 168 Page 3 cc:

Ellis W. Merschoff Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani Project Manager U. S. Nuclear Regulatory Commission 1 White Flint North, Mail Stop 07-D I 11555 Rockville Place Washington, DC 20555 Cornelius F. O'Keefe c/o U. S. Nuclear Regulatory Commission P. 0. Box 910 Bay City, TX 77404-0910 A. H. Gutterman, Esquire Morgan, Lewis 1111 Pennsylvania Avenue, N.W.

Washington, DC 20004 M. T. Hardt/W. C. Gunst City Public Service P. 0. Box 1771 San Antonio, TX 78296 A. Ramirez/C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Jon C. Wood Matthews & Branscomb 112 East Pecan, Suite 1100 San Antonio, Texas 78205-3692 Institute of Nuclear Power Operations - Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 Richard A. Ratliff Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 R. L. Balcom/D. G. Tees Reliant Energy, Inc.

P. 0. Box 1700 Houston, TX 77251 C. A. Johnson/A. C. Bakken, Ill AEP - Central Power and Light Company P. 0. Box 289, Mail Code: N5012 Wadsworth, TX 77483 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

NOC-AE-01001 168 ATTACHMENT 1 DESCRIPTION OF CHANGES AND SAFETY EVALUATION

NOC-AE-01001168 Page 2 1.0 Introduction The proposed amendment will revise various Technical Specifications to eliminate shutdown actions associated with radiation monitoring instrumentation. The proposed changes will enhance plant reliability by reducing its exposure to unnecessary shutdowns and increase operational flexibility. Inoperable radiation monitoring instrumentation has little or no direct effect on plant safety and generally there are effective compensatory actions that can be taken for inoperable radiation monitoring instrumentation.

The proposed changes to the STP Technical Specifications are based in part on the Westinghouse Standard Improved Technical Specifications (NUJREG-143 1). STP's plant-specific differences are described and justified below.

2.0 Description Each of the proposed changes to the Technical Specifications is described in Table 1.

3.0

Background

STPNOC believes that the overall reliability of the plant can be enhanced by the elimination of unnecessarily restrictive TS requirements for radiation monitors. An overview of the basis for each of the proposed changes is provided in Table 1.

4.0 Technical Analysis A technical review of each of the proposed changes described in Table 1 is provided below. The review identifies the affected instrumentation, describes its function, including relevant references to the STP UFSAR, and provides a technical justification for the proposed change.

STPNOC is not proposing the changes described in this application as risk-informed changes to be reviewed in conformance with the criteria of Regulatory Guides 1.174 and 1.177. Where risk information for initiating events is presented, it is clear that their likelihood is very small. The compensatory actions proposed are based largely on the requirements that have already been accepted in other industry applications based on NUREG-1431. In addition, the radiation monitors affected by the proposed changes are not modeled in the STP PRA so there is no detailed risk quantification. STPNOC applied deterministic and risk insights to rank the affected radiation monitors as either non-risk significant or low safety-significant.

Corresponding Bases changes will be provided subsequent to NRC approval of the proposed changes.

NOC-AE-01001 168 Page 3 Control Room Intake Air Radioactivity (Table 3.3-3 ACTION 28 for Functional Unit 10.d)

The STP design includes two redundant channels for the subject function. Descriptions of these monitors (RE/RT-8033, 8034) are found in Sections 7.3.2 and 11.5.2.3.4 of the STP UFSAR:

7.3.2 Control Room Envelope HVAC ESFAS The ESFAS for the Control Room Envelope HVAC System uses the control room/EAB ventilation radiation monitors to sense whether predetermined setpoints have been exceeded. If they are, or if the Westinghouse ESFAS has generated a safety injection signal, this ESFAS sends actuation signals to the appropriate control room envelope HVAC components. The ESFAS meets the requirements of GDC 13, 19, 20, 21 and 22.

7.3.2.1 Description. The ESFAS for the Control Room Envelope HVAC System receives high radiation signals from the redundant control room/EAB ventilation radiation monitors and the safety injection signal from the Nuclear Steam Supply System (NSSS) ESFAS. Upon receipt of any of these signals, the control room makeup air is diverted through the makeup filters and then, along with a portion of the recirculation air, through cleanup filters. For a complete description of the Control Room Envelope HVAC System and its operation, refer to Section 9.4.1. Section 6.4 provides an analysis of Control Room Envelope habitability. Section 11.5 provides a description of the radiation monitors.

11.5.2.3.4 Control Room Electrical Auxiliary Building Ventilation Monitors:

The CR/EAB ventilation monitors are Class 1E monitors that continuously assess the intake air to the CR for indication of abnormal airborne radioactivity concentration. Each monitor assembly is powered from a separate electrical power source. In the event of high radiation CR emergency ventilation operation is initiated (Section 7.3.2). Failure of a monitor is alarmed in the CR.

STPNOC proposes that the TS for these monitors be revised to change the time required to place the Control Room Makeup and Cleanup Filtration System in the recirculation and makeup mode from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 7 days should there be one less than the minimum required channels operable (i.e., 1 of 2 channels inoperable). This proposed extension in the time to place the system in recirculation and makeup is consistent with the requirements in NUREG-1431. This is technically acceptable since there is still an operable channel that will function to realign the control room envelope on a high radiation signal unless the failure mode is due to the output power supply. However, in that case, the operator can manually initiate the function. The 7 day allowed outage time

NOC-AE-01001168 Page 4 in the NUREG is based on the low probability of a Design Basis Accident (DBA) occurring during this time period, and ability of the remaining train to provide the required capability.

STPNOC also proposes to revise the time required to realign the Control Room Makeup and Cleanup Filtration System to the recirculation and makeup mode from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months should there be two less than the minimum required channels operable (i.e., 2 of 2 channels inoperable). The worst case configuration is that all trains of Control Room HVAC (TS 3.7.7) would be considered inoperable. The current allowed outage time for that configuration is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . This proposed change would make the radiation monitoring allowed outage time consistent with the allowed outage time for the condition where all trains of Control Room HVAC are inoperable. STPNOC provided that justification in the applications that resulted in the issuance of Amendments 125/113 (Reference 3).

The proposed TS actions also recognize a fuel handling accident as a potential release initiator and require that movement of irradiated fuel assemblies and crane operations with loads over the spent fuel pool be suspended when the required action to realign the system cannot be accomplished in the allowed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Radiation Monitoring Instrumentation for Plant Operations (TS 3/4.3.3)

The specific features of this TS are discussed below. STPNOC proposes to delete this TS in its entirety as discussed below and in Table 1.

Containment Atmosphere Radioactivity - High (Table 3.3-6, Functional Unit 1.a)

This function is performed by RT-801 1, which is comprised of three detectors, RE-801 1A (particulate), RE-801 1B (iodine), & RE-801 1C (noble gas). The instruments are described in the STP UFSAR Section 11.5.2.3.2 and Table 11.5-1.

These instruments have no actuation function. Except for the iodine detector, RE 801 lB, the instruments governed by this TS are the same instruments required by TS 3/4.4.6.1, and Functional Unit L.b, discussed below. STPNOC proposes to delete the requirements of TS 3/4.3.3 and Table 3.3-6 that pertain to these instruments and address them in TS 3/4.4.6.1.

This will effectively eliminate the Technical Specification requirements for the iodine monitoring function, RE-801 1B, which is acceptable because this instrument serves no actuation function and has no significant role in accident mitigation.

NOC-AE-01001168 Page 5 RCS Leakage Detection (Table 3.3-6 Functional Unit 1.b)

The detectors that perform this function are RE-801 1A (particulate) and 801 IC (noble gas). As discussed in Table 1, STPNOC proposes to simply relocate the requirements for these instruments to TS 3/4.4.6.1.

In addition, STPNOC proposes to delete the requirement to perform the monthly Digital Channel Operational Test (DCOT) surveillance on the radiation detection instrumentation associated with the RCS leakage detection system. Radiation monitors at STP are highly reliable digital processors with extensive self diagnosis capabilities. Historical records for these monitors indicate that the monthly DCOT surveillance has not identified any unknown existing failures.

Because of this, the monthly DCOT function can be extended to 18 months.

STPNOC proposes to delete the DCOT requirement since the 18 month calibration requirement encompasses the DCOT requirements.

Accident Monitoring Instrumentation (Table 3.3-10)

Containment High Range Radiation Monitor (Functional Unit 17)

The function of the Containment High Range Radiation Monitor (RE/RT-8050, 8051) is to detect, monitor, indicate and alarm radiation level inside containment.

These monitors are listed in UFSAR Table 7B3-1 as RG 1.97 Category Al instruments. The instruments perform a post-accident monitoring function and have no actuation functions. The proposed required action is consistent with NUREG-1431 except for the time allowed for submitting the special report, and reflects the low probability of an accident requiring the monitors and the ability to establish a temporary alternative.

Steam Line Radiation Monitors (Functional Unit 16)

The steam line radiation monitors (RE/RT-8046, 8047, 8048, and 8049) are listed in UFSAR Table 7B.3 - 1 as RG 1.97 Category Al instruments. The detectors detect, monitor, indicate and alarm radiation level for main steam lines. The steam generator blowdown radiation monitors described below are identified in UFSAR Table 11.5-2 as being functionally redundant to the steam line radiation monitors.

Steam Generator Blowdown Radiation Monitors (Functional Unit 22)

The steam generator blowdown radiation monitors (RE/RT-8022, 8023, 8024, and 8025) are listed in UFSAR Table 7B.3 - I as RG 1.97 Category Al instruments.

The instruments detect, monitor, indicate and alarm radiation level for steam generator blowdown lines. The steam line monitors described above are

NOC-AE-01001168 Page 6 identified in UFSAR Table 11.5-2 as being functionally redundant to the steam generator blowdown radiation monitors.

There is adequate redundancy of radiation monitoring functions on the secondary side of the plant. Requiring a shutdown for inoperable radiation monitoring instrumentation does not contribute to plant safety, and may have negative effect because of the transient cycle a shutdown causes. The proposed requirements are consistent with the requirements in NUREG-1431 for monitoring instrumentation for which an alternate means of monitoring is acceptable.

The required report for the subject inoperable instrumentation will outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to OPERABLE status.

STPNOC proposes that the report be a 30 day report instead of the 14 days described in NUREG-1431. There is no safety significance associated with the time allocated to submit a report and 30 days is a more reasonable time to prepare, review, and submit the report.

5.0 Regulatory Safety Analysis 5.1 No Significant Hazards Determination STPNOC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10CFR50.92, "Issuance of amendment," as discussed below.

1)

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The radiation monitors affected by the proposed amendment are not potential accident initiators. Adequate measures are available to compensate for radiation monitors that are out of service. The proposed amendment does not affect how the affected radiation monitors function or their role in the response of an operator to an accident or transient. The core damage frequency in the STP PRA is not impacted by the proposed changes. Therefore, STPNOC concludes that there is no significant increase in the probability or consequences of an accident previously evaluated.

NOC-AE-01001168 Page 7

2)

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The radiation monitors affected by the proposed amendment are not credited for the prevention of any accident not evaluated in the safety analysis. The proposed amendment involves no changes in the way the plant is operated or controlled. It involves no change in the design configuration of the plant. No new operating environments are created. Therefore, STPNOC concludes the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3)

Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change has no significant effect on functions that are supported by the affected radiation monitors. There will be no significant effect on the availability and reliability of the affected radiation monitors. Adequate measures are available to compensate for radiation monitors that are out of service.

Therefore, STPNOC concludes the proposed change does not involve a significant reduction in the margin of safety.

Conclusion Based upon the analysis provided herein, the proposed amendments do not involve a significant hazards consideration.

5.2 Applicable Regulatory Requirements/Criteria Control Room Envelope Isolation Actuation:

The control room envelope is assumed in the accident analyses to be actuated to the filtered makeup and recirculation mode in a DBA to maintain doses to the operators below the limits of GDC 19. The radiation monitor actuation of the control room HVAC is an ESFAS function and is subject to the requirements of GDC 2, 4, 20 through 24, and 10 CFR 50.55a(h)(2).

The proposed changes to the Technical Specifications would not change the function of the affected radiation monitors and there is no significant impact on compliance with the regulatory requirements.

NOC-AE-01001168 Page 8 RCS Leakage Detection Instrumentation:

GDC 30 of Appendix A to 10 CFR 50 requires means for detecting and, to the extent practical, identifying the location of the source of RCS leakage. Regulatory Guide 1.45 describes acceptable methods for selecting leakage detection systems.

STPNOC's proposed changes to the RCS leakage detection radiation monitoring instrumentation do not affect how the monitors perform their function.

Accident Monitoring Instrumentation:

Required accident monitoring instrumentation ensures that there is sufficient information available on selected unit parameters to monitor and to assess unit status and behavior following an accident. These essential instruments are identified in the STP UFSAR where it addresses the recommendations of Regulatory Guide 1.97 as required by Supplement 1 to NUREG-0737.

The instrument channels required to be OPERABLE by TS 3.3.3.6 include two classes of parameters identified during unit specific implementation of Regulatory Guide 1.97 as Type A and Category I variables.

Type A variables are included in this LCO because they provide the primary information required for the control room operator to take specific manually controlled actions for which no automatic control is provided, and that are required for safety systems to accomplish their safety functions for DBAs.

Category I variables are the key variables deemed risk significant because they are needed to:

Determine whether other systems important to safety are performing their intended functions; Provide information to the operators that will enable them to determine the likelihood of a gross breach of the barriers to radioactivity release; and Provide information regarding the release of radioactive materials to allow for early indication of the need to initiate action necessary to protect the public, and to estimate the magnitude of any impending threat.

There is adequate redundancy of radiation monitoring functions on the secondary side of the plant. In addition, STPNOC applied deterministic and risk insights to rank the steam generator blowdown radiation monitors as non-risk-significant and the main steam line radiation monitors as low safety significant. The proposed changes to the Technical

NOC-AE-01001168 Page 9 Specifications would not change the function of the affected radiation monitors and there is no significant impact on compliance with the regulatory requirements.

6.0 Environmental Considerations 10 CFR 51.22(b) specifies the criteria for categorical exclusion from the requirements for a specific environmental assessment per 10 CFR 51.21. This amendment request meets the criteria specified in 10 CFR 51.22(c)(9). The specific criteria contained in this section are discussed below.

(i) the amendment involves no significant hazards consideration As demonstrated in the No Significant Hazards Consideration Determination, the requested license amendment does not involve any significant hazards consideration.

(ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite The requested license amendment involves no change to the facility and does not involve any change in the manner of operation of any plant systems involving the generation, collection or processing of radioactive materials or other types of effluents. Therefore, no increase in the amounts of effluents or new types of effluents would be created.

(iii) there is no significant increase in individual or cumulative occupational radiation exposure The requested license amendment involves no change to the facility and will not increase the radiation dose resulting from the operation of any plant system.

Furthermore, implementation of this proposed change will not involve work activities that could contribute to occupational radiation exposure. Therefore, there will be no increase in individual or cumulative occupational radiation exposure associated with this proposed change.

Based on the above it is concluded that there will be no impact on the environment resulting from this change. The change meets the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to specific environmental assessment by the Commission.

NOC-AE-O100 1168 Page 10 7.0 References

1. NUREG-1431 "Standard Technical Specifications, Westinghouse Plants"

2. South Texas Project Updated Final Safety Analysis Report, Revision 8

3. Application for License Amendment dated September 28, 1998 as supplemented on April 22, 1999, April 27, 2000 and August 15, 2000 (NOC-AE-000305, NOC-AE 000513, NOC-AE-00000822, NOC-AE-00000902)

NOC-AE-01001168 Attachment I Page 11

'T'hl* 1 Page Affected Section Description of Change Reason for Change 3/4 3-28 Table 3.3-3, ACTION 28 applies to Control Room Intake Air Radioactivity-The proposed change allows for additional operational flexibility in ACTION High. With less than the minimum channels operable, the situations where one or more channels of Control Room Ventilation STATEMENTS, ACTION currently requires initiation of the Control Room radiation monitoring are inoperable. The seven days proposed in ACTION ACTION 28 for Makeup and Cleanup Filtration System in the recirculation and 28.a. is consistent with the provisions of NUREG-1431. The 12-hour AOT Functional Unit makeup filtration mode within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The proposed change proposed in ACTION 28.b. is consistent with 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AOT that is I0.d would split ACTION 28 into ACTION 28.a. 28.b., 28.c., and currently allowed in TS 3.7.7 for conditions where all trains of control 28.d. ACTION 28.a. would apply when the number of operable room ventilation are inoperable. ACTION 28.c. and 28.d. are new channels is one less than the minimum channels operable requirements that clarify the required action if the recirculation and requirement and would extend the time allowed to place the filtration mode cannot be implemented.

system into the recirculation and filtration mode to 7 days.

ACTION 28.b. would apply when the number of operable channels is two less than the minimum channels operable requirement and would allow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to place the system in the recirculation and filtration mode. ACTION 28.c. would provide a required action and time to shutdown to MODE 5 and to suspend movement of irradiated fuel assemblies and crane operation with loads over the spent fuel pool if ACTION 28.a.

or 28.b. were not met in MODE 1, 2, 3, or 4. ACTION 28.d.

would provide a required action to suspend CORE ALTERATIONS, crane operation with loads over the spent fuel pool, or movement of irradiated fuel assemblies if ACTION 28.a. or 28.b. were not met in MODE 5 or 6.

I___

I TS 3/4.3.3 defines the requirements for radiation monitoring instrumentation for plant operations and applies to the Containment Atmosphere Radioactivity-High and RCS Leakage Detection instrumentation. The current TS action for the Containment Radioactivity-High function allows continued operation for up to 30 days provided grab samples are obtained and analyzed. The required action after 30 days is not specified. Table 4.3-3 specifies the surveillance requirements for the instrumentation. STPNOC proposes to delete TS 3/4.3.3, Table 3.3-6, and Table 4.3-3. The Containment Atmosphere Radioactivity-High instrumentation would be deleted from the TS, and the requirements for the RCS Leakage Detection instrumentation would be relocated to TS 3/4.4.6. 1, as discussed below. In addition, the monthly DCOT for the gaseous and particulate monitoring systems would be eliminated.

The proposed change eliminates an implied, ii not explicit, srnutdown action for the Containment Atmosphere Radioactivity-High instrumentation. There is no justification for TS action for this instrumentation since it has no actuation function and there are no operator actions credited in the safety analyses that depend on this function.

Because of the elimination of an unnecessary shutdown action, this is viewed as a reliability enhancement.

The elimination of the DCOT surveillance requirement is a reduction of unnecessary burden and is justified by operational experience. This change is less restrictive than NUREG-143 I, which requires a quarterly surveillance.

3/4 3-50, 3-51,3 52, 3-53 TS 3/4.3.3, Table 3.3-6 Table 4.3-3

NOC-AE-0100 1168 Page 12 Page Affected Section Description of Change Reason for Change 3/4 3-50, TS 3/4.3.3, TS 3/4.3.3 defines the requirements for radiation monitoring The relocation of the RCS Leakage Detection instrumentation requirements 3-51, 52, Table 3.3-6 instrumentation for plant operations and applies to the RCS to TS 3/4.4.6.1 is an administrative change and is more convenient for the 53 Table 4.3-3 Leakage Detection instrumentation. The current TS for the RCS operators using the Technical Specifications.

3/4 4-19 TS 3/4.4.6.1 Leakage Detection instrumentation invokes the ACTION requirements for TS 3.4.6.1, RCS Leakage Detection Systems.

Table 4.3-3 specifies the surveillance requirements for the instrumentation. As mentioned above, STPNOC proposes to delete TS 3/4.3.3, Table 3.3-6, and Table 4.3-3 and relocate the RCS Leakage Detection Instrumentation requirements to TS 3/4.4.6.1.

3/4 3-69 Table 3.3-10 The current TS include shutdown actions for Containment-High The proposed changes enhance plant reliability by removing an 3/4 3-71 Range Radiation Monitor (ACTION 39a. and 39b). STPNOC unnecessary shutdown action. The proposed changes are consistent with proposes to change ACTION 39a. (one less than the total the requirements of NUREG-1431.

number of channels requirements for the Containment-High Range instrument) to have a required action of a report to the Commission if the channel cannot be restored in 30 days.

ACTION 39b, (number of channels less than the minimum channels operable requirement) would be changed to require a report to the Commission if at least one inoperable channel cannot be restored to operable status within 7 days.

3/4 3-69 Table 3.3-10 The current TS include shutdown actions for Steam Line The elimination of the shutdown actions associated with these radiation 3/4 3-71 Radiation Monitors and Steam Generator Blowdown Radiation monitoring instruments is considered to increase plant reliability. There is Monitors (ACTION 40). STPNOC proposes to revise ACTION adequate redundancy of radiation monitoring functions on the secondary 40 to include ACTION 40a. and 40b. ACTION 40a. would side of the plant. Requiring a shutdown for inoperable radiation apply when the number for operable channels is less than the monitoring instrumentation does not contribute to plant safety, and may minimum channels operable requirement and when a diverse have negative effect because of the transient cycle it causes. The proposed channel is functional. The action would require a report to the requirements are consistent with the requirements in NUREG-1431 for Commission if at least one inoperable channel could not be monitoring instrumentation for which an alternate means of monitoring is restored in 30 days. ACTION 40b. would apply when the acceptable.

number of operable channels is less than the minimum channels operable requirement and the diverse channel is not functional.

In this case, the action would be to restore at least one inoperable channel to operable status within 7 days or prepare a report to the Commission.

NOC-AE-01001 168 Page 1 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES

NOC-AE-01001168 Page 2 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/42-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Deleted 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - FQ(Z) 3/4 2-5 FIGURE 3.2-2 K(Z) - NORMALIZED FQ (Z) AS A FUNCTION OF CORE HEIGHT..

Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-10 3/4.2.5 DNB PARAMETERS 3/42-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 TABLE 3.3-2 (This table number not used) 3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-29 TABLE 3.3-5 (This table number not used) 3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-42 3/4.3.3 MI1TORP-;_G T1"'DTI'R "I

WAr TT ON-NOT USED Radiati-n M:nit-e*ng f*or Plant Operatio, 3/4 3-50 TABLE 3.3 6 RAIA~LTION MO0NITORING INSTRARANTATIO FOd Dt ^ UT cOE IA tC NOT USED 3/4 3-51 TABLE 1.3 3 RADItTION MNITORItN*Gt INtSTRUMENTATION FOR PLAONTt OPRAT IONtS STR'TT t ^Zt DrEbtrtt '4BTW6 NOT USED 3/4 3-53 Movable Incore Detectors 3/4 3-54 SOUTH TEXAS -UNITS 1 & 2 v

Unit 1 - Amendment No. 27-,,

99 Unit 2 - Amendment No. 4,49, 86

NOC-AE-01001 168 Page 3 NO CHANGES ON THIS PAGE.

INCLUDED FOR COMPLETENESS.

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 0

TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES 3 (1/train) 2 (1/train) 3 (1/train)

All See Item 1. above for all Safety Injection initiating functions and requirements.

3 2

2 1

3 2

All All See Item 8. above for all Loss of Power initiating functions and requirements.

11. FHB HVAC

a. Manual Initiation

b. Automatic Actuation Logic and Actuation Relays

c. Safety Injection

d. Spent Fuel Pool Exhaust Radioactivity - High It, 3 (1/train) 3 2 (1/train) 2 3 (1/train) 3 1, 2, 3, 4 or with irradiated fuel in spent pool 1, 2, 3, 4 or with irradiated fuel in spent pool 29,30 29,30 See Item 1. above for all Safety Injection initiating functions and requirements.

2 I

2 With irradiated 30 fuel in spent fuel pool

10. Control Room Ventilation

a. Manual Initiation

b. Safety Injection

c. Automatic Actuation Logic Sand Actuation Relays

d. Control Room Intake Air Radioactivity - High

e. Loss of Power ACTION 27 27 28

NOC-AE-01001168 Page 4 TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACIION 26 ACTION 27 ACTION 28-ACTION 29 ACTION 30-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected Auxiliary Feedwater Pump inoperable and take ACTION required by Specification 3.7.1.2.

For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.7.

a. With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within 4-helu 7 days initiate and maintain operation of the Control Room Makeup and Cleanup Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.

b. With the number of OPERABLE channels two less than the Minimum Channels OPERABLE requirement, within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months initiate and maintain operation of the Control Room Makeup and Cleanup Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.

c.

With required ACTION 28a. or 28b. not met in MODE 1, 2,3, or 4, suspend movement of irradiated fuel assemblies and crane operations with loads over the spent fuel pool, AND be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in MODE 5 in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

d.

With required ACTION 28a. or 28b. not met in MODE 5 or 6, suspend CORE ALTERATIONS, movement of irradiated fuel assemblies, and crane operations with loads over the spent fuel pool.

For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.8.

With irradiated fuel in the spent fuel pool: With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the FHB exhaust air filtration system is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.

SOUTH TEXAS - UNITS I & 2 3/4 3-28 Unit 1 Amendment No. 4-25 Unit 2 - Amendment No.A)-

NOC-AE-01001168 Page 5 INSTRUMENTATION 3/4.3.3 M0Nfl9TDUIG lTDST RLraFNTAIZ NOT USED ADIATION MONITORING FOR PLANT OPERATIONS LIMIT CONDITION FOR OPERATION 3.3.3.1 The ra *ation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall bPERABLE with their Alarm/Trip Setpoints within the specified limits.

APPLICABILITY:

As s wn in Table 3.3-6.

ACTION:

a.

With a radiation monitorin hannel Alarm/Trip Setpoint for plant operations exceeding the value shown in ble 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the cha I inoperable.

b.

With one or more radiation monitoring annels for plant operations inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 are not app ble.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operati s shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHA EL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODE nd at the frequencies shown in Table 4.3-3.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-50 Unit I Amendment No.

Unit 2 Amendment No.

NOC-AE-0l1001168 Page 6 TABLE 3.3-6 NOT USED 0

RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS CHANNELS MINIMUM TO TRIP/

CHANNELS APPLICABLE ALARM/TRIP FUNCTIONAL UNIT A

M OPERABLE MODES SETPOINT ACTION

1. Containment

a. Containment Atmosphere N.A 31 Radioactivity - High

b. RCS Leakage Detection

1. Particulate N.A.

1 1,2,3,4 34 Radioactivity

2. Gaseous N.A.

1 1,2,3,4 N.A.

Radioactivity 0'0C 0

0

NOC-AE-01001168 Page 7 PAGE INTENTIONALLY BLANK TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 31 -

ith less than the Minimum Channels OPERABLE requirement, op tion may continue for up to 30 days provided grab samples of the c ainment atmosphere are obtained and analyzed at least once p 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Grab samples are not required to be obtained for the ation of containment pressurization for an Integrated Leak Rate st (ILRT) provided that a grab sample is obtained and analyzed at start of depressurization of 2

containment following the IL ACTION 32 -

(Not Used)

ACTION 33 -

(Not Used)

ACTION 34 -

Must satisfy the ACTION requirement for Specification 3

.1.

SOUTH TEXAS - UNITS I & 2 3/4 3-52 Unit 1 - Amendment No. M Unit 2 - Amendment No. 4-5

NOC-AE-0100 1168 Page 8 TABLE 4.3-3 NOT USED 0

H RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS DIGITAL Z

CHANNEL MODES FOR WHICH S"HCHANNEL CHANNEL OPERATIONAL SURVEILLANCE

-FUNCTIONAL UNIT CK CALIBRATION TEST IS REQUIRED

1. Containment

a. Containment Atmosphere S

R M

All Radioactivity - High

b. RCS Leakage Detection

1) Particulate Radioactivity S1,2,3,4 SR 1,2,3,4

2) Gaseous Radioactivity zz 0 0

NOC-AE-01001168 Page 9 NO CHANGES ON THIS PAGE.

INCLUDED FOR COMPLETENESS.

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

13. Containment Water Level (Narrow Range)

14. Containment Water Level (Wide Range)

15. Core Exit Thermocouples

16. Steam Line Radiation Monitor

17. Containment - High Range Radiation Monitor

18. Reactor Vessel Water Level (RVWL)

19. Neutron Flux (Extended Range)

20. Containment Hydrogen Concentration

21. Containment Pressure (Extended Range)

22. Steam Generator Blowdown Radiation Monitor

23. Neutron Flux - Startup Rate (Extended Range)

TOTAL NO.

OF CHANNELS 2

3

- 2 I/steam line 2

2*

2 2

2 1/blowdown line 2

MINIMUM CHANNELS OPERABLE I

I

- 1 1/steam line I

1*

1 1

1/blowdown line 1

A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the upper section section and three or more in the lower section, are OPERABLE.

- A channel is OPERABLE if at least two core exit thermocouples per core quadrant are OPERABLE, and at least one quadrant has at least four OPERABLE thermocouples SOUTH TEXAS - UNITS 1 & 2 3/4 3-69 Unit 1 - Amendment No. 77 Unit 2 - Amendment No. 66 I

ACTION 36 37 42 40 39 41 36 36 36 40 36

NOC-AE-0100 1168 Page 10 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

ACTION 39 -

a.

With the number of OPERABLE channels one less than the Total Number of Channels requirements, restore one inoperable channel to OPERABLE status within 730 days, or be in -af least H4O TSHTDOWNwithin thle next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

b.

With the number of OPERABLE channels less than the Minimum Channels Operable requirements, restore at least one inoperable channel to OPERABLE status within 72-hu-s 7 days or be in at least HOT1 SHTn'-,

N within the next 12 hour-submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

ACTION 40 -

a.

With the number of OPERABLE channels less than the Minimum Channels Operable requirements and with a functional diverse channel, restore at least one inoperable channel to OPERABLE status within 72-hours 30 days, or be in at !Least HOTSHUTDOWN.ithin the next 12 heuros submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

b.

With the number of OPERABLE channels less than the Minimum Channels Operable requirements and with the diverse channel not functional, restore at least one inoperable channel to OPERABLE status within 7 days or submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status ACTION 41 -

a.

With the number of OPERABLE channels one less than the Required Number of Channels, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory;

2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and

3.

Restore the system to OPERABLE status at the next scheduled refueling.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-71 Unit I - Amendment No. 7q7 Unit 2 - Amendment No. 66

NOC-AE-01001168 Page 11 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

ACTION 42 -

a.

With one required channel inoperable, restore the required channel to OPERABLE status within 30 days; otherwise, a report shall be prepared and submitted in accordance with Specification 6.9.2 within the next 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

b.

With two required channels inoperable, restore one required channel to OPERABLE status within 7 days; otherwise, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 43 -

a.

With the number of OPERABLE channels two less than the Total Number of Channels requirements, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE channels three less than the Total Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels less than the Minimum Channels Operable requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

[No changed requirements - simply rolled ACTION 42 to the next page]

SOUTH TEXAS - UNITS I & 2 3/4 3-72 Unit 1 - Amendment No. 7 Unit 2 - Amendment No. 66

NOC-AE-01001168 Page 12 REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Instrumentation shall be OPERABLE:

a.

One Containment Atmosphere Radioactivity Monitor (gaseous or particulate), and

b.

The Containment Normal Sump Level and Flow Monitoring System.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With the required containment atmosphere radioactivity monitor inoperable perform the following actions or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s:

1)

Restore one containment atmosphere monitoring system to OPERABLE status within 30 days

and,

2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or

3)

Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the required containment normal sump level and flow monitoring system inoperable perform the following actions or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s:

1)

Restore the containment normal sump and flow monitoring system to OPERABLE status within 30 days and,

2)

Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With both a. and b. inoperable, enter 3.0.3.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a.

Containment Atmesphere gaseous and Paricul-ateMniongStesprrmnefCH NL CHECK, CHANNEL CALIBRATION, AND DIGITtL CHANNEL OPERATIONAL TEST at the frequendies specified in Table 41.3 3, and

a.

Containment Atmosphere Gaseous and Particulate Monitoring Systems performance of the following:

1)

CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

2)

CHANNEL CALIBRATION at least once per 18 months

b.

Containment Normal Sump Level and Flow Monitoring System performance of CHANNEL CALIBRATION at least once per 18 months.

SOUTH TEXAS - UNITS I & 2 3/4 4-19 Unit I - Amendment No. 86 Unit 2 - Amendment No. 7-3

NOC-AE-01001168 ATTACHMENT 3 TECHNICAL SPECIFICATION PAGE WITH PROPOSED CHANGES INCORPORATED

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Deleted 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR -FQ(Z) 3/4 2-5 FIGURE 3.2-2 K(Z) - NORMALIZED FQ (Z) AS A FUNCTION OF CORE HEIGHT.,

Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-10 3/4.2.5 DNB PARAMETERS 3/42-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 TABLE 3.3-2 (This table number not used) 3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-16 TABLE 3.3--3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-29 TABLE 3.3-5 (This table number not used) 3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-42 3/4.3.3 Not Used 3/4 3-50 TABLE 3.3-6 Table Not Used 3/4 3-51 TABLE 4.3-3 Table Not Used 3/4 3-53 Movable Incore Detectors 3/4 3-54 SOUTH TEXAS - UNITS 1 & 2 v

Unit 1 - Amendment No.

Unit 2 - Amendment No.

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACITION 26-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected Auxiliary Feedwater Pump inoperable and take ACTION required by Specification 3.7.1.2.

ACTION 27-For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.7.

ACTION 28-a)

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within 7 days initiate and maintain operation of the Control Room Makeup and Cleanup Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.

b)

With the number of OPERABLE Channels two less than the Minimum Channels OPERABLE requirement, within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months initiate and maintain operation of the Control Room Makeup and Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.

c)

With required ACTION 28a. or 28b. not met in MODE 1, 2, 3, or 4, suspend movement of irradiated fuel assemblies and crane operations with loads over the spent fuel pool, and be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in MODE 5 in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d)

With required ACTION 28a. or 28b. not met in MODE 5 or 6, suspend CORE ALTERATIONS, movement of irradiated fuel assemblies and crane operations with loads over the spent fuel pool.

ACTION 29-For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.8.

ACTION 30- With irradiated fuel in the spent fuel pool: With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the FHB exhaust air filtration system is in operation and discharging through at least one train of HEPA filters and charcoal absorbers.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-28 Unit 1 - Amendment No.

Unit 2 - Amendment No.

INSTRUMENTATION 3/4.3.3 (Not Used)

SOUTH TEXAS - UNITS 1 & 2 3/4 3-50 Unit 1 Amendment No.

Unit 2 Amendment No.

"0 H

z SOUTH TEXAS - UNITS I & 2 3/4 3-51 Unit 1 - Amendment No.

Unit 2 - Amendment No.

PAGE INTENTIONALLY BLANK SOUTH TEXAS - UNITS 1 & 2 3/4 3-52 Unit 1 - Amendment No.

Unit 2 - Amendment No.

0 z SOUTH TEXAS - UNITS 1 & 2 3/43-53 Unit I Amendment No.

Unit 2 Amendment No.

TABLE 3.3-10 (Continued)

ACTION 39 -

ACTION 40 -

a.

ACTION 41-SOUTH TEXAS ACTION STATEMENTS (Continued)

a.

With the number of OPERABLE channels one less than the Total Number of Channels requirements, restore one inoperable channel to OPERABLE status within 30 days, or submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable instrumentation channels to OPERABLE status.

b.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements, restore at least one inoperable channel to OPERABLE status within 7 days, or submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable instrumentation channels to OPERABLE status.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements and with a functional diverse Channel, restore at least one inoperable channel to OPERABLE status within 30 days, or submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable instrumentation channels to OPERABLE status.

b.

With the number of Channels less than the Minimum Channels OPERABLE requirement, and with the diverse channel not functional, restore at least one inoperable Channel to operable status within 7 days or submit a report in accordance with Specification 6.9.2 within the next 30 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable instrumentation channels to OPERABLE status.

a.

With the number of OPERABLE channels one less than the Required Number of Channels, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory;

2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and

3.

Restore the system to OPERABLE status at the next scheduled refueling.

- UNITS I & 2 3/4 3-71 Unit 1 - Amendment No.

Unit 2 - Amendment No.

TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

ACTION 42-a.

With one required channel inoperable, restore the required channel to OPERABLE status within 30 days; otherwise, a report shall be prepared and submitted in accordance with Specification 6.9.2 within the next 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

b.

With two required channels inoperable, restore one required channel to OPERABLE status within 7 days; otherwise, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 43 -

a.

With the number of OPERABLE channels two less than the Total Number of Channels requirements, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE channels three less than the Total Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels less than the Minimum Channels Operable requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SOUTH TEXAS - UNITS 1 & 2 3/4 3-72 Unit I - Amendment No.

Unit 2 - Amendment No.

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Instrumentation shall be OPERABLE:

a.

One Containment Atmosphere Radioactivity Monitor (gaseous or particulate), and

b.

The Containment Normal Sump Level and Flow Monitoring System.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With the required containment atmosphere radioactivity monitor inoperable perform the following actions or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s:

1)

Restore one containment atmosphere monitoring system to OPERABLE status within 30 days

and,

2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or

3)

Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the required containment normal sump level and flow monitoring system inoperable perform the following actions or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s:

1)

Restore the containment normal sump and flow monitoring system to OPERABLE status within 30 days and,

2)

Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With both a. and b. inoperable, enter 3.0.3.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a.

Containment Atmosphere Gaseous and Particulate Monitoring Systems performance of the following:

1)

CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

2)

CHANNEL CALIBRATION at least once per 18 months

b.

Containment Normal Sump Level and Flow Monitoring System performance of CHANNEL CALIBRATION at least once per 18 months.

SOUTH TEXAS - UNITS I & 2 3/4 4-19 Unit I - Amendment No.

Unit 2 - Amendment No.

ML020580493

Text

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