NOC-AE-03001647, Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days

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Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days
ML033520526
Person / Time
Site: South Texas STP Nuclear Operating Company icon.png
Issue date: 12/15/2003
From: Jordan T
South Texas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-03001647
Download: ML033520526 (27)
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Text

Nuclear Operating Company SourhTeh Irc/ectEkcnIcGcnavmS42bon P.O BAn28o9 Jwdstb Ts77483 December 15, 2003 NOC-AE-03001647 10CFR50.36 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Unit 2 Docket No. STN 50499 Proposed Emergency Change to Technical Specification 3.8.1.1 Pursuant to 10 CFR 50.90 and 10 CFR 50.91(a)(6), STP Nuclear Operating Company (STPNOC) requests an emergency amendment to the STP Unit 2 Operating License NPF-80. The proposed changes to the Technical Specifications (TS) would revise TS 3.8.1, "AC Sources - Operating," to extend the allowed outage time (AOT) for Unit 2 Standby Diesel Generator (SDG) 22 from 14 days to 61 days. STPNOC is proposing this change as a one-time change.

During a surveillance test on December 9, 2003, SDG-22 experienced a failure and STPNOC does not expect to be able to complete the repairs in the current 14 day AOT. The attached evaluation justifies an extension of the AOT for up to 47 additional days (61 days total AOT).

The proposed license amendments are needed to avoid a potential shutdown in accordance with TS 3.8.1 at the expiration of the AOT, which would require STP Unit 2 to be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, STPNOC requests approval of this license amendment application on an emergency basis and issuance of the amendment no later than December 22, 2003 to allow implementation prior to expiration of the AOT on December 23, 2003.

This TS revision request represents a risk-informed licensing change. The proposed change meets the criteria of Regulatory Guide RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" and Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants".

The STPNOC Plant Operations Review Committee has 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.

03001647 (SDG-22 61day AOT).doc STI: 31680107 A Ys

NOC-AE-03001647 Page 2 If there are any questions regarding the proposed amendment, please contact Mr. A. WV. Harrison at (361) 972-7298 or me at (361) 972-7902.

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

Executed on Pecierj4l 2003 date Vice President Engineering & Technical Services awh/

Attachments:

1. Description of Changes and Safety Evaluation
2. Annotated Technical Specification Pages
3. Revised Technical Specification Pages
4. Commitments

NOC-AE-03001647 Page 3 cc:

(paper copy) (electronic copy)

Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 L. D. Blaylock Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission David H. Jaffe Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Texas Genco, LP Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP Texas Central Company Jeffrey Cruz Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MNI 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704

Description of Changes and Safety Evaluation NOC-AE-03001647 Attachment I Page 1 1.0 Description Pursuant to 10 CFR 50.90 and 10 CFR 50.91(a)(6), STP Nuclear Operating Company (STPNOC) requests an emergency amendment to the STP Unit 2 Operating License NPF-80.

The proposed changes to the Technical Specifications (TS) would revise TS 3.8.1, "AC Sources - Operating," to extend the allowed outage time (AOT) for Unit 2 Standby Diesel Generator (SDG) 22 from 14 days to 61 days. STPNOC is proposing this change as a one-time change.

During a surveillance test on December 9, 2003, SDG-22 experienced a failure and STPNOC does not expect to be able to complete the repairs in the current 14 day AOT. The maintenance activities are being worked on a 24-hour per day schedule until completed.

Emergency approval of the proposed license amendments is needed to avoid a potential shutdown in accordance with TS 3.8.1 at the expiration of the AOT on December 23, 2003. ACTION 3.8.1.1.b would require STP Unit 2 to be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

STPNOC could not reasonably have foreseen or anticipated the failure of SDG-22.

Therefore, STPNOC requests approval of this license amendment application on an emergency basis and issuance of the amendment no later than December 22, 2003 to allow implementation prior to expiration of the AOT on December 23, 2003.

This TS revision request represents a risk-informed licensing change. The proposed change meets the criteria of Regulatory Guide RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" and Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants".

2.0 Proposed Change Proposed Change The proposed change adds a footnote to TS 3.8.1.1 .b to permit a one-time extension to the AOT for SDG-22 as shown below.

b. With a standby diesel generator inoperable, demonstrate the OPERABILITY of the above-required A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE standby diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.2) for each such standby diesel generator separately within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless it can be demonstrated there is no common mode failure for the remaining diesel generator(s). Restore the inoperable standby diesel generator to OPERABLE

NOC-AE-03001647 Attachment 1 Page 2 status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.P'~

Note to appear on TS page 3/4 8-7:

(12) For the Unit 2 Train B standby diesel generator (SDG-22) failure of December 9, 2003, restore the inoperable standby diesel generator to OPERABLE status within 61 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0 Background 3.1 Electrical Power Systems On-site AC Sources Description STP UFSAR Sec. 8.3.1.1.4 provides an overview of the on-site AC sources (standby diesel generators):

Onsite Standby Power Supply and ESF Power Distribution: The Onsite Standby Power Supply Systems of Units 1 and 2 each consist of three independent, physically separated, SBDGs supplying power to three associated load groups designated Train A, Train B, and Train C. Each load group consists of a 4.16 kV ESF bus and the electrical loads connected to that bus. The Onsite Standby Power Supply Systems of Units 1 and 2 operate independently of each other. Each SBDG and load group of a particular unit is also physically separated and electrically independent from the other two SBDGs and their load groups. Each train (i.e.,

Load Group) is independent but is not totally redundant; two trains are necessary to mitigate the consequences of a design basis accident (DBA). Qualification of all Class IE electrical equipment which is a part of the Onsite Standby Power Supply and ESF Power Distribution System is discussed in Sections 3.10 and 3.11.

Each SBDG is located in a separate room of the Diesel Generator Building (DGB), which is a seismic Category I structure (described in Section 3.8.4).

Each 4.16 kV ESF bus is provided with switching that permits energization of the bus by five alternative sources:

1. The respective unit auxiliary transformer
2. No. 1 standby transformer
3. No. 2 standby transformer
4. Standby diesel generator
5. 138 kV emergency transformer Each SBDG is automatically started in the event of loss of offsite power (LOOP) or safety injection (SI) signal, as described in Section 8.3.1.1.4.4, and the required Class IE loads connected to that ESF bus are automatically connected in a predetermined time sequence.

Each SBDG is ready to accept load within 10 seconds after the start signal.

NOC-AE-03001647 Attachment 1 Page 3 The SBDGs are not used for peaking and therefore the design complies with Branch Technical Position (BTP) Instrumentation and Controls System Branch (ICSB) 8.

3.2 Past Performance Prior to the failure of SDG-22, STP Unit 2 Emergency Diesel Generators have not exhibited any unusual performance issues over the past 3 years.

The NRC Performance Indicator for Emergency AC Power tracks the cumulative unavailability for these diesels over a rolling 3 year period. Unit 2 Emergency Diesel Generators have performed at (or very close to) the industry average, which has significant margin to the performance indicator threshold.

3.3 SDG-22 Failure During a surveillance run on December 9, 2003, SDG-22 experienced a failure, which included ejection of a number of major components. Because of the extent of damage to the diesel, STPNOC plans to disassemble the SDG and repair or replace the damaged components.

STPNOC is performing an extensive evaluation of the cause of the event. To date, STPNOC has no positive evidence of, or reason to suspect a common-mode failure. If the results change prior to approval of this amendment, STPNOC will promptly advise the NRC and withdraw the proposed amendment. If the results change subsequent to issuance of the amendment, STPNOC will promptly evaluate the operability of the potentially affected SDGs and apply the requirements of the Technical Specifications.

Repair Schedule:

The repair duration is expected to be 61 days if replacement of the crankshaft is not required. STPNOC expects to have an initial assessment of the condition of the crankshaft by December 19, 2003. Final assessment of the condition will conclude on or about December 31, 2003. If replacement is required, STPNOC will inform the NRC of the situation and take appropriate action. If necessary, STPNOC will expeditiously supplement the application.

The maintenance activities are being worked on a 24-hour per day schedule until completed. STPNOC is focusing management attention to assure the work is performed with the required high level of quality.

NOC-AE-03001647 Attachment 1 Page 4 4.0 Technical Analysis 4.1 Electrical Power Systems AC Sources Safety Analysis Basis The initial conditions of DBA and transient analyses in the FSAR, Chapter 6 and Chapter 15, assume ESF systems are OPERABLE. The AC electrical power sources are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF systems so that the fuel, Reactor Coolant System (RCS), and containment design limits are not exceeded.

The OPERABILITY of the AC electrical power sources is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the unit. In Modes 1, 2, 3, and 4 this results in maintaining at least two trains of the onsite or one train of the offsite AC sources OPERABLE during accident conditions in the event of:

a. An assumed loss of all offsite power or all onsite AC power; and
b. A worst case single failure.

The extended allowed outage time (EAOT) of 14 days in TS 3.8.1.1b includes a combination of deterministic and risk-informed bases justified by the redundancy of the plant design and the extremely low probability of an event that cannot be mitigated by one operable ESF train.

The EAOT is typically adequate for emergent conditions and planned maintenance.

However, the duration of the repair of SDG-22 for the current condition is expected to exceed 14 days.

4.2 Deterministic Evaluation (Defense in Depth and Safety Margins)

During the extended repair period, design basis accident (DBA) AC power requirements can be met with the operable A and C train SDGs, assuming no single failure.

In addition, the deterministic component of the basis for the EAOT provides assurance that the plant retains a substantial capability to mitigate design basis events with the reduced capability that results from postulating a DBA and a single failure while the plant is in the EAOT, or from postulating an accident (with no single failure) in the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by TS 3.8.1 .1 .d for inoperability of required equipment in one of the other trains.

This evaluation shows that a single operable ESF train can mitigate (at a reduced capacity in certain cases) the design basis accidents except for a large break LOCA where the break is located in the RCS loop associated with the operating train of safety injection.

Because postulation of these events is beyond the design basis of the plant, in some cases the deterministic analyses apply less conservative acceptance criteria than those required of design basis analyses. These capabilities were described in detail in STP's license amendment application to extend the SDG AOT to 14 days, which was approved in Amendments 85/72 to the STP Operating Licenses. The information in Table I

NOC-AE-03001647 Attachment I Page 5 summarizes the limitations identified in the deterministic evaluations. The information in Table I was previously submitted in STP's letter dated January 4, 1996 (ST-HL-AE-5261) in support of the 14 day AOT amendment and in STP's letter of intent for risk-informed Technical Specifications dated March 18, 2003 (NOC-AE-03001458).

Spent Fuel Pool Cooling SDG-22 provides emergency power for one of the two 100% trains of Spent Fuel Pool Cooling (SFPC). In the event of a loss of off-site power, SDG-23 for Train C would provide adequate power for its associated train of SFPC. Should there be a single failure of SDG-23 or other required SFPC component with the postulated loss of off-site power, the heat-up rate of the SFP will be very slow (-1 F/hr). The time to boil from the current SFP temperature (83YF) is 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br />. Restoration of off-site power would be expected well before boiling would occur.

In addition to the margin described above, compensatory actions as described in Section 4.4 will be taken in order to minimize the small increase in risk during the period when SDG-22 is inoperable.

Based on these evaluations, STPNOC has concluded that the proposed change maintains essentially the same defense-in-depth and safety margins that were determined to be acceptable in the review and approval for extending the original AOT to 14 days.

NOC-AE-03001647 Attachment I Page 6 TA~h1I 1DThterminiktic (Thnnhilitv with One Innnernhie- SDC1 and Assuring Single Failure

',~ystem, - .tu'nction :Affecteu :'~--:- AUifitiraVe'AcUon *,' MM~;

UIIIVI Safety Injection Cannot mitigate LBLOCA if None (minimal cooling from One train in maintenance outage (LHSI and HHSI) the SI train is injecting into using hot leg recirculation) One train fails the broken RCS loop One train injects into the broken loop Safety Injection Steam line break mitigation None required DNB not expected to occur (HHSI) capability reduced Safety Injection Cannot mitigate SBLOCA Operator action per EOPs to One train in maintenance.

(LHSI and HHSI) without operator action if the depressurize One train fails.

SI train is injecting into the One train of HHSI not enough to match broken RCS loop break flow Operator action is expected to be effective Residual Heat Cannot provide long term Continue to inject using LHSI RHR is required approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Removal cooling if only a single ESF until RHR is restored. after event. Recovery of power to ESF bus bus is energized or if RHR is is expected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> injecting into broken loop Containment Spray Iodine removal during a Monitor TSC doses and LBLOCA or SBLOCA relocate to lower dose area Control Room Cannot maintain 1/8" positive None Positive pressure is expected to be Envelope HVAC pressure maintained, so system is expected to be functional Fuel Handling Cannot provide filter path for Provide alternate power Procedure in place for establishing cross-Building HVAC recirculation phase leakage if supply from operable diesel connect.

C train is only operable train Component CCW flow to RCFC's and Manually isolate non-safety If train C is the operable train, CCW flow Cooling Water RHR Heat Exchanger less header to restore design flow. approximates design flow. Effect of than design reduced CCW flow is slight even without I__________________ I_____________________________

_____________m anual action.

These conditions require an initiating event (i.e., Large Break LOCA) with a loss of offsite power and failure of a standby diesel generator given a diesel generator is unavailable for its extended AOT.

NOC-AE-03001647 Attachment I Page 7 4.3 Probabilistic Risk Assessment (PRA) Evaluation Evaluation of Risk Impact Risk-informed considerations for the proposed change consist of:

  • Maintaining defense-in-depth,
  • Continuation of the STP configuration risk management program to control performance of other risk significant tasks during the SDG maintenance, and
  • Consideration of specific compensatory measures to minimize risk.

The risk impact of the proposed change for extending the SDG-22 AOT for up to 47 additional days (61 days total) has been evaluated and found to be acceptable. The overall risk impact is within acceptable limits of current regulatory guidance. The effect on risk of the proposed increase in completion time for maintenance of SDG-22 has been evaluated using Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" and RG 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants".

RG 1.174 Evaluation The proposed change has been evaluated in accordance RG 1.174 by applying the "three-tier" approach.

Tier 1 - PRA Capability and Calculation of Risk Insights Tier 2 - Avoidance of Risk-Significant Plant Configurations Tier 3 - Risk-Informed Configuration Risk Management Tier 1: PRA Capability and Calculation of Risk Insights PRA Capability As described in more detail below, the STP PRA is a complete Level 1 and Level 2 at-power model that includes external events. Consideration of plant operating modes other than Mode 1 is not necessary for the requested extension in the Allowed Outage Time.

The STP PRA is a full-scope, at-power (Plant MODE 1 and MODE 2) Level 1 /2 PRA that incorporates internal events, inclusive of fires/floods, and external events (seismic, fire, flood). STP's PRA features a seismic PRA, flood/fire PRA (including spatial interactions analysis), human reliability analysis, and detailed common cause modeling. The model is quantified using the RISKMAN software code that has met

NOC-AE-03001647 Attachment I Page 8 station and industry software quality assurance requirements. The PRA is maintained and updated under a PRA configuration control program in accordance with station procedures. The station's PRA program and associated processes are governed by procedure. Periodic reviews and updates, if necessary, are performed for plant changes (including as a minimum, performance data, procedures, and plant modifications) by qualified personnel with independent reviews and approvals. As described below, the STP PRA has undergone a recent industry Peer Review.

STPNOC has used its PRA for risk-informed insights and applications since the mid-1980s. The NRC has previously reviewed the STP PRA in support of approving the following risk-informed licensing applications:

1. Amendment Nos. 59 & 47, dated February 17, 1994 (initial application made in 1990). The application extended the allowed outage times for 10 LCOs and the intervals for 3 surveillance tests.
2. Amendment Nos. 85 & 72, dated October 31, 1996. The application extended the allowed outage time for the standby diesel generators and their associated support systems.
3. Amendment Nos. 125 & 113, dated September 26, 2000. The application relaxed LCO requirements for control room and fuel handling building HVAC.
4. Approval of Exemption to Special Treatment Requirements, dated August 3, 2001. The application relaxed regulatory requirements for various degrees of special treatment provisions for safety related components (Option 2 Pilot).
5. Amendment Nos. 135 & 124, dated January 10, 2002. The application extended the allowed outage time for ECCS Accumulators consistent with WCAP-15049-A and relaxed accumulator surveillance requirements consistent with Westinghouse Improved Technical Specifications.
6. Amendment Nos. 143 & 131, dated September 17, 2002. The application allowed a one-time extension of integrated leak rate test to 15 years.
7. Amendment Nos. 146 & 134, dated December 31, 2002. The application extended the allowed outage time for auxiliary feedwater.
8. Amendment Nos. 158 & 146, dated December 2, 2003. The application eliminated the UFSAR description of the turbine missile design basis.

In addition to the risk-informed licensing applications above, STPNOC has used the STP PRA to provide additional insight to other license amendments and to respond to NRC questions.

The following references are evaluations of the STP PRA that have been performed by the NRC and others:

1. NRC SER related to the STP Probabilistic Safety Assessment, dated January 21, 1992, documented favorable conclusions with regard to the STP PRA, including its treatment of fire (done to support the review for Amendment Nos. 59 & 47, above).

NOC-AE-03001 647 Attachment 1 Page 9

2. 2002 Peer Review In April 2002, STP's PRA underwent an industry peer review performed in accordance with NEI-00-02, "Industry PRA Peer Review Process." All technical elements within the scope of the peer review were graded as sufficient to support application requiring the capabilities of a grade 2 (e.g., risk ranking applications).

Most of the elements were further graded as sufficient to support application requiring the capabilities defined for grade 3 (e.g., risk-informed applications supported by deterministic insights). The general assessment of the peer reviewers was that STP's PRA could effectively be used to support applications involving risk significance determinations supported by deterministic analyses once the items noted in the element summaries and Fact & Observations (F&O) sheets were addressed. Using STP's Corrective Action program as a tracking mechanism, the F&O items identified by the peer team that could affect this application have been completed and are incorporated into the latest revision of the STP PRA (Revision 4). The STP PRA Revision 4 model is the basis for this application of Risk-Informed Technical Specifications.

STPNOC is confident that the STP PRA is acceptable for the risk assessment performed for this application.

Uncertainty Analysis and Sensitivity Analysis Uncertainty Analysis An uncertainty analysis on Core Damage Frequency (CDF) is performed for every PRA model update. The uncertainty parameters for PRA model STP Revision 4 CDF areas follows:

Mean 9.1E-06 5th 4.2E-06 Median 8.1E-06 9 5 th 1.7E-05 Range Factor 2.0 This uncertainty represents the classic aleatory or parameter uncertainty.

For this application, a detailed uncertainty analysis was not performed; however, a test case was evaluated that assumed the change in CDF with SDG-22 out of service could be represented by a log normal distribution with a range factor of

10. The resultant uncertainty distribution for the sum of the base case CDF and the delta CDF with SDG-22 out-of-service can then be represented by a log-normal distribution with the following parameters:

NOC-AE-03001647 Attachment 1 Page 10 Mean 1.2E-05 5th 4.8E-06 Median 9.8E-06 9 5 th 2.OE-05 Range Factor 2.0 This test case shows that assuming a log normal distribution with a range factor of 10 for the core damage frequency change with SDG-22 out of service does not affect the results of the analysis presented above and does not affect the margin available to the Regulatory Guide 1.174 total CDF limit of 1.OE-04.

Sensitivity Analysis As part of the Risk Significance Categorization Process associated with the STP exemption from special treatment requirements, a series of sensitivity studies are performed. These include:

  • Evaluation of operator recovery actions,
  • Evaluation of common cause modeling
  • Evaluation of planned maintenance configurations, and
  • Evaluation of data (values and uncertainty).

The changes in the PRA model associated with the proposed amendment request were compared to the sensitivity evaluations mentioned above to determine if any conclusions would be invalidated or significantly affected. The results of this evaluation are that no significant equipment importance changes result from this temporary plant condition.

Calculation of Risk Insights Regulatory Guide 1.174 describes a general approach to risk-informed regulatory decision-making and contains different acceptance criteria using changes in core damage frequency and large early release frequency.

STP used the guidance contained in RG 1.174 for permanent changes to facilities even though this Technical Specification change request is for a temporary condition.

The results of the risk analysis performed for the 61 day extended AOT meet the acceptance criteria contained in RG 1.174 as shown below. Application of the risk criteria for a permanent change is conservative for a temporary change.

Because the SDG-22 condition is limited in time, the ACDF and the ALERF are multiplied by the expected 47-day extension of the AOT to obtain a conditional probability. The conditional probability is treated as a ACDF and ALERF for the

NOC-AE-03001647 Attachment 1 Page 11 evaluation against RG 1.174. The PRA evaluation for extending the AOT an additional 47 days was performed assuming "zero maintenance" for that time.

The table below depicts the acceptance criteria of RG 1.174 and the results calculated for the proposed change.

ACDF Total CDF ALERF Total LERF STP Unit 2 before - 9.lE-06/yr - 5.2E-07/yr proposed change Results with 47 2.8E-06 1.2E-05 2.IE-07 7.3E-07 days additional AOT_

RG 1.174 Criteria >1.OE-06/yr <1.OE-04/yr. >1.OE-07/yr <1.OE-05/yr

<1.OE-05/yr I _ <1.OE-06/yr These values are well within the criteria established in RG 1.174.

Severe Weather Considerations The STP PRA model loss of offsite power (LOOP) frequency includes causes of LOOP and incorporates site specific grid recovery information. STP has not experienced a LOOP as defined and analyzed in the PRA(i.e. loss of power in the switchyard and safety busses, with a plant trip). The frequency and duration of LOOP events are based in part on conditions, such as severe weather, external to the plant and specific to the plant location. Severe weather events typically have longer durations for recovery because of the possibility of widespread effects but occur less frequently than other causes of LOOP. Severe weather events at the South Texas Project location are dominated by high winds caused by tornados and hurricanes. Tornadoes can occur any time during a year, but typically occur most frequently between March and June. The hurricane season runs from May to early November. The most likely causes of loss of offsite power from severe weather should have a lower likelihood of occurrence for the duration of the repairs to the emergency diesel generator. This effect is not included in the quantification presented above.

The site-specific long-term forecast is consistent with the considerations above.

STPNOC's weather service contractor has advised STP that the temperatures may be about 1-3 degrees below normal through February across southeast Texas.

Minimum temperature is expected to reach 23°F-27°F along mid to upper Texas coast, 21TF -25TF across the Houston area and 16'F -20'F across northern and western portions of southeast Texas. The probability of significant icing across southeast Texas for January is 10%, and for January and February is 15%.

NOC-AE-03001647 Attachment I Page 12 Tier 2: Avoidance of Risk-Significant Plant Configurations There is reasonable assurance that risk-significant plant equipment configurations will not occur when SDG-22 is out of service (OOS) consistent with the proposed TS change. Increases in risk posed by potential combinations of equipment OOS will be managed by the CRMP.

The compensatory measures delineated in Section 4.4 are structured to avoid risk significant plant configurations during the SDG-22 outage. This is achieved by minimizing planned maintenance activities that could have adverse risk impacts and by ensuring that key equipment necessary to respond to loss of offsite power events (e.g., turbine driven auxiliary feedwater pump) remain available for service.

Tier 3: Risk-informed Configuration Risk Management STP's Configuration Risk Management Program ensures that on-line risk levels are appropriately evaluated prior to performing any maintenance activity. This program provides guidance for managing plant trip risk, nuclear safety risk, and safety function degradation from on-line maintenance, external or internal conditions, as required by 10 CFR 50.65(a)(4) of the Maintenance Rule. The procedure addresses risk management practices in maintenance planning and execution. Additional detail is provided in Section 4.4 of this application.

RG 1.182 Evaluation:

RG 1.182 and RG 1.160 are used in conjunction with NUMARC 93-01 as standards for implementation of 10CFR50.65 (Maintenance Rule). Section 11.3.7.2 of NUMARC 93-01 includes recommended quantitative risk action thresholds for maintenance activities, as reproduced in the table below.

Incremental Incremental Large Early

[Conditional] Core [Conditional] Release Damage Probability Probability (ILERP)l (ICDP)'

> 1E-05 Configuration should not > IE-06 normally be entered voluntarily IE IE-05

  • Assess non- IE IE-06 quantifiable factors
  • Establish risk management actions

< IE-06 Normal work controls < 1E-07 Note 1: For clarity and consistency of terms, the term "conditional" is added to the table heading. The calculated ICDP includes the quantified effect of the maintenance configuration (condition).

NOC-AE-03001647 Attachment 1 Pagc 13 The ICDP for the proposed change is 2.8E-06, which is within the IE IE-05 range and the ILERP for the proposed change is 2.1E-07, which is within the IE lE-06 range. As described in Section 4.4 of this application, STPNOC will address the non-quantifiable factors and establish risk management actions.

PRA Evaluation Conclusions The final results of the risk evaluation were compared with the risk significance criteria from RGs 1.1 74 and 1.182. The calculated values for ACDF and ALERF demonstrate that the proposed SDG-22 completion time change has an acceptably small quantitative impact on plant risk.

Station risk levels remain low (near baseline values) and manageable with sufficient margin to allow remedial and corrective actions to be implemented in the event unplanned equipment outages occur. Therefore, it is concluded that, based on the small quantitative plant risk impact and the compensatory measures described in Section 4.4, the risk associated with the SDG-22 outage does not impose a significant risk to public health and safety.

4.4 Risk Management, Including Compensatory Actions and Consideration of Non-quantifiable factors The proposed action conforms to the requirements of the STP Configuration Risk Management Program (CRMP). The CRMP is controlled by procedure OPGP03ZA0091, "Configuration Risk Management Program". South Texas will continue to use the CRMP to evaluate and monitor the risk significance associated with extending the SDG-22 AOT.

The CRMP requires the compensatory measures listed below to be implemented if the Non-Risk Significant Threshold of 1.OE-6 is exceeded. The STP CRMP satisfies the Maintenance Rule requirements as specified in 10CR50.65(a)(4).

  • Notify the Duty Operations and Duty Plant Manager
  • Identify and implement compensatory measures approved by the Duty Plant Manager. Compensatory measures may include but are not limited to the following:

- Reduce the duration of the risk sensitive activities

- Remove risk sensitive activities from the planned work scope

- Reschedule work activities to avoid high risk sensitive equipment outages or maintenance states

- Accelerate the restoration of out-of-service equipment

- Determine and establish the safest plant configuration

- Establish contingency plan to reduce the effects of the degradation of the affected SSC(s) by utilizing the following:

  • Operator actions

NOC-AE-0300 1647 Attachment I Page 14

  • Increased awareness of plant configuration concerns and the effects of certain activities and transients on plant stability
  • Administrative controls
  • Ensure availability of functionally redundant equipment
  • Ensure any measures taken to reduce risk are recorded in the Control Room Logbook.
  • Heighten station awareness of plant conditions and evolutions as deemed necessary by the Duty Plant Manager.

In addition to the risk management actions described above, the compensatory actions listed below are to be implemented for unplanned entry into extended AOTs for SDGs in accordance with procedure OPOPO1ZO0006, "Extended Allowed Outage Time".

STPNOC has already initiated these actions for this situation, which is an unplanned entry into an extended AOT. If any changes to these actions are required, STPNOC will assess and manage the risk in accordance with the CRMP, which implements 10CFR50.65(a)(4).

  • Notification of the transmission/distribution service providers (TDSP) of the condition and of the maintenance restrictions required for the STP switchyard.
  • Hang EAOT protected train signs.
  • Planned maintenance on required systems, subsystems, trains, components, and devices that depend on the other trains of equipment during the EAOT SHALL NOT be performed.
  • No maintenance that could result in an inoperable OPEN containment penetration.
  • Containment purges shall be for pressure control only and for short duration.
  • No planned maintenance on the Unit 2 TSC DG.
  • No planned maintenance on Load Center 2W.
  • No planned maintenance on MCC 2G8.
  • No planned maintenance on the Positive Displacement Charging Pump (PDP).
  • No planned maintenance on the Emergency Transformer OR the 138KV Blessing to STP AND Lane City to Bay City lines.
  • No maintenance activities in the switchyard that could directly cause a Loss Of Offsite Power event unless required to ensure the continued reliability and availability of the offsite power sources.
  • Attempt to VERIFY that the station is NOT under hurricane, tornado, or flood watches or warnings. (Note that weather was addressed earlier in this application and no severe weather is currently forecast.)
  • Attempt to VERIFY with the TDSP that NO adverse weather conditions exist in the areas of our offsite power supplies that challenge the stability of grid.
  • ENSURE the Work Schedule contains NO planned maintenance on SWGR 2L or 2K.

NOC-AE-0300 1647 Attachment 1 Page 15 The PRA evaluation for extending the AOT an additional 47 days was performed assuming "zero maintenance" for that time. While SDG-22 is inoperable beyond its normal 14 day AOT, STPNOC will suspend planned maintenance of components that could affect the risk calculated for the 47-day extension.

If A or C train components required by TS are found to be inoperable, STPNOC will apply the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ACTION of TS 3.8.1.1.d as required and perform corrective maintenance to restore the components within the TS 3.8.1.1.d required action times or follow the shutdown action required by the TS. For B train components required by TS found to be inoperable, STPNOC will apply the appropriate TS and perform corrective maintenance in accordance with the required action times for that TS. If no TS applies, STPNOC will restore the component to operable status as promptly as practical.

STP will monitor changes in planned risk levels using the CRMP. During the extended AOT, the calculated average CDF levels will be updated in the event unplanned maintenance is required on equipment within the scope of the CRMP. Risk levels will be monitored throughout the SDG-22 outage and STP will comply with the risk threshold actions required by the CRMP [Commitment]. In addition, STPNOC will keep the NRC Resident Inspector apprised of deviations from the expected risk profile for the duration of the SDG-22 repair.

STPNOC is not proposing in this application to change the requirements of any Technical Specification other than the one-time change to TS 3.8.1.1.b. STPNOC will continue to comply with the TS requirements for STP Unit 2.

In addition, STP has reviewed the STP Unit 2 surveillance requirements (SR) scheduled to be performed during the extended allowed outage time to assure that performing the SRs will not affect the basis for the proposed amendment. This surveillance review consisted of a look-ahead (both from a risk and Technical Specification compliance perspective) at planned U-2 surveillance testing for the time period of the proposed allowed outage time extension to determine whether the surveillance test would render the tested equipment inoperable, and if so, whether the tested equipment would remain functional. STPNOC determined that equipment scheduled for SRs during the extended AOT would be functional while the SR is performed except for the SRs for Train B SSPS. STPNOC plans to perform the Train B SSPS SRs and the results presented above include the effects of performing the Train B SRs.

STPNOC would generally expect to perform SRs for equipment that will remain functional during the SR (e.g., starting the other SDGs). STPNOC will apply TS 3.8.1. 1.d as necessary to perform SRs for Train A and Train C components where the component is functional but does not meet the TS definition of OPERABLE. However, STPNOC plans to apply the allowed SR grace interval as needed to defer SRs that have a higher potential for reactor trip and short duration LCO times. Although the equipment subject to the deferred surveillances can be maintained functional during the SR, STPNOC believes that nuclear safety is increased by maintaining the components in an

NOC-AE-03001647 Attachment I Page 16 operable condition. In accordance with the TS, STPNOC will not extend any SR beyond its grace period.

5.0 Regulatory Analysis 5.1 No Significant Hazards Consideration In 10 CFR 50.92(c), the Nuclear Regulatory Commission (NRC) provides the following standards to be used in determining the existence of a significant hazards consideration:

... a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22, or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in the margin of safety.

STPNOC has reviewed the proposed amendment request and determined that its adoption does not involve a significant hazards consideration based upon the following discussion:

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

Response: No.

SDG-22 provides onsite electrical power to vital systems should offsite electrical power be interrupted. It is not an initiator to any accident previously evaluated.

Therefore, this extended period of operation with the SDG out-of-service will not increase the probability of an accident previously evaluated.

The SDGs act to mitigate the consequences of design basis accidents that assume a loss of offsite power. For that purpose, redundant SDGs are provided to protect against a single-failure. During the Technical Specification 14 day allowed outage time, an operating unit is allowed by the Technical Specifications to remove one of the SDGs from service, thereby losing this single-failure protection. This operating condition is considered acceptable. The consequences of a design basis accident coincident with a failure of the redundant SDG during the additional 47-day period are the same as those during the 14 day allowed outage time. Therefore, during the period of the extended AOT, there is no significant increase in consequences of an accident previously evaluated.

Therefore, the proposed change will not involve significant increase in the probability or consequences of an accident previously evaluated.

NOC-AE-03001647 Attachment I Page 17

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

Response: No.

There are no new failure modes or mechanisms created due to plant operation for an extended period to perform repairs and post-maintenance testing of SDG-22.

Extended operation with an inoperable SDG-22 does not involve any modification in the operational limits or physical design of plant systems. There are no new accident precursors generated due to the extended allowed completion time.

Therefore, 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.

Plant operation for an additional 47 days beyond the existing AOT for inoperable SDG-22, has been shown to have a very small impact on plant risk using the criteria of RG 1.174 and RG 1.182. During the extended allowed outage time, the electrical power system maintains the ability to perform its safety function of providing an available source of power to the Engineered Safety Feature (ESF) systems as assumed in the accident analyses. During the extended maintenance and test period, appropriate compensatory measures will be implemented to restrict risk significant activities.

Therefore, the proposed change does not involve a significant reduction in a margin of safety as defined in the basis for any Technical Specification.

5.2 Applicable Regulatory Requirements/Criteria With the implementation of the proposed change, STP Unit 2 continues to meet applicable design criteria. The proposed change is a one-time extension to the TS AOT.

It does not affect the design basis of the plant. In addition, STP Unit 2 will remain within the scope of the TS Limiting Conditions for Operation and is still subject to the requirements of the action statements.

Since the mid-1980s, the NRC has been reviewing and granting improvements to TS that are based, at least in part, on PRA insights. In its final policy statement on TS improvements of July 22, 1993, the NRC stated that it expects that licensees, in preparing their Technical Specification related submittals, will utilize any plant-specific PSA (probabilistic safety assessment) or risk survey and any available literature on risk insights and PSAs. Similarly, the NRC staff will also employ risk insights and PSAs in evaluating Technical Specification related submittals. Further, as a part of the

NOC-AE-03001647 Attachment 1 Page 18 Commission's ongoing program of improving Technical Specifications, it will continue to consider methods to make better use of risk and reliability information for defining future generic Technical Specification requirements. The NRC reiterated this point when it issued the revision to 10 CFR 50.36, "Technical Specifications," in July 1995.

In August 1995, the NRC adopted a final policy statement on the use of PRA methods in nuclear regulatory activities that improve safety decision making and regulatory efficiency. The PRA policy statement included the following points:

1. The use of PRA technology should be increased in all regulatory matters to the extent supported by state-of-the-art in PRA methods and data and in a manner that compliments the NRC's deterministic approach and supports the NRC's traditional defense-in-depth philosophy.
2. PRA and associated analyses (e.g., sensitivity studies, uncertainty analyses, and importance measures) should be used in regulatory matters, where practical within the bounds of the state-of-the-art, to reduce unnecessary conservatism associated with current regulatory requirements.
3. PRA evaluations in support of regulatory decisions should be as realistic as practicable and appropriate supporting data should be publicly available for review.

In conclusion, based on the deterministic and PRA considerations discussed in this submittal, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 Environmental Consideration STPNOC has evaluated the proposed changes and determined the changes do not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (3) a significant increase in the individual or cumulative occupational exposure. Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9),

and an environmental assessment of the proposed changes is not required.

Annotated Technical Specification Pages NOC-AE-03001647 Attachment 2 Page 1 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E Distribution System(1), and
b. Three separate and independent standby diesel generators, each with a separate fuel tank containing a minimum volume of 60,500 gallons of fuel.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one offsite circuit of the above-required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With a standby diesel generator inoperable, demonstrate the OPERABILITY of the above-required A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE standby diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.2) for each such standby diesel generator separately within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless it can be demonstrated there is no common mode failure for the remaining diesel generator(s). Restore the inoperable standby diesel generator to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."12
c. With one offsite circuit of the above-required A.C. electrical power sources and one standby diesel generator inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Specification 4.8.1.1.1a. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive SOUTH TEXAS - UNITS 1 & 2 3/4 8-1 Unit 1 - Amendment No. 68, 85 Unit 2 - Amendment No. i7, 72

NOC-AE-03001647 Attachment 2 Page 2 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE (Not used)

SPECIFICATION NOTATIONS

(') Loss of one 13.8 kV Standby Bus to 4.16 kV ESF bus line constitutes loss of one offsite source. Loss of two 13.8 kV Standby busses to 4.16 kV ESF bus lines constitutes loss of two offsite sources.

(2) All diesel generator starts for the purpose of these surveillances may be preceded by a prelube period.

(3) A diesel generator start in less than or equal to 10 seconds (fast start) shall be performed every 184 days. All other diesel generator starts for the purpose of this surveillance may be modified starts involving reduced fuel (load limit) and/or idling and gradual acceleration to synchronous speed.

(4) Generator loading may be accomplished in accordance with vendor recommendations, including a warmup period prior to loading.

(5) The diesel generator start for this surveillance may be a modified start (see SR 4.8.1.1 .2a.2)).

(6) Momentary transients outside this load range due to changing conditions on the grid shall not invalidate the test.

(7) If Specification 4.8.1.1 .2a.2) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the standby diesel generator may be operated at 5000-5500 kW for a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperature has stabilized.

(8) (Not used)

(9) (Not used)

(10) This test may be performed during power operation provided that the other two diesel generators are operable.

(11) Credit may be taken for events that satisfy any of these Surveillance Requirements.

Uit 2-Train Bstandbyde1sbehg'eniate r (SD.2)filure of D6ce'mbe ,'2003,

.sto're'heiinoperable stan'dby Id iseI greratrioOP,,ERABLE 'status within 61 ays or bejin at least HOT.SHUTDOWNkw'thinnthe"rext12 housand in.GOLD'SHU.TDOWN Witiln tle.,following 24-hours.

SOUTH TEXAS - UNITS 1 & 2 3/4 8-7 Unit 1 - Amendment No. 68, 122 Unit 2 - Amendment No. 67,110

Revised Technical Specification Pages NOC-AE-03001647 Attachment 3 Revised Technical Specification Pages

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E Distribution System(1), and
b. Three separate and independent standby diesel generators, each with a separate fuel tank containing a minimum volume of 60,500 gallons of fuel.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one offsite circuit of the above-required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With a standby diesel generator inoperable, demonstrate the OPERABILITY of the above-required A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE standby diesel generators by performing Surveillance Requirement 4.8.1.1 .2.a.2) for each such standby diesel generator separately within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless it can be demonstrated there is no common mode failure for the remaining diesel generator(s). Restore the inoperable standby diesel generator to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.(12 )
c. With one offsite circuit of the above-required A.C. electrical power sources and one standby diesel generator inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Specification 4.8.1.1.1 a. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive SOUTH TEXAS - UNITS 1 & 2 3/4 8-1 Unit 1 - Amendment No. 68, 85 Unit 2 - Amendment No. A, 72

TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE (Not used)

SPECIFICATION NOTATIONS (1) Loss of one 13.8 kV Standby Bus to 4.16 kV ESF bus line constitutes loss of one offsite source. Loss of two 13.8 kV Standby busses to 4.16 kV ESF bus lines constitutes loss of two offsite sources.

(2) All diesel generator starts for the purpose of these surveillances may be preceded by a prelube period.

(3) A diesel generator start in less than or equal to 10 seconds (fast start) shall be performed every 184 days. All other diesel generator starts for the purpose of this surveillance may be modified starts involving reduced fuel (load limit) and/or idling and gradual acceleration to synchronous speed.

(4) Generator loading may be accomplished in accordance with vendor recommendations, including a warmup period prior to loading.

(5) The diesel generator start for this surveillance may be a modified start (see SR 4.8.1.1 .2a.2)).

(6) Momentary transients outside this load range due to changing conditions on the grid shall not invalidate the test.

7) If Specification 4.8.1.1.2a.2) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the standby diesel generator may be operated at 5000-5500 kW for a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperature has stabilized.

(8) (Not used)

(9) (Not used)

(10) This test may be performed during power operation provided that the other two diesel generators are operable.

(11) Credit may be taken for events that satisfy any of these Surveillance Requirements.

(12) For the Unit 2 Train B standby diesel generator (SDG-22) failure of December 9, 2003, restore the inoperable standby diesel generator to OPERABLE status within 61 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SOUTH TEXAS - UNITS 1 & 2 3/4 8-7 Unit 1 - Amendment No. 68- 122 Unit 2 - Amendment No. 57,110

Commitments NOC-AE-03001647 Attachment 4 Commitments

1. STP will monitor changes in planned risk levels using the CRMP. During the extended AOT, the calculated average CDF levels will be updated in the event unplanned maintenance is required on equipment within the scope of the CRMP. Risk levels will be monitored throughout the SDG-22 outage and STP will comply with the risk threshold actions required by the CRMP. In addition, STPNOC will keep the NRC Resident Inspector apprised of deviations from the expected risk profile for the duration of the SDG-22 repair.
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