IR 05000498/2012003

IR 05000498-12-003 & 05000499-12-003, on 03/31/2012 - 06/29/12, South Texas Project Electric Generating Station, Units 1 & 2, Integrated Resident & Regional Report, Operability Evaluations & Functionality Assessments & Followup of Events

ML12215A215
Person / Time
Site:	South Texas
Issue date:	08/02/2012
From:	Walker W C NRC/RGN-IV/DRP/RPB-C
To:	Richards K D South Texas
Walker W
References
IR-12-003
Download: ML12215A215 (48)

Text

August 2, 2012

Mr. Kevin President and Chief Executive Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483 Subject: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION

- NRC INTEGRATED INSPECTION REPORT 05000 498/20 12 00 3 AND 05000499/20 12 00 3

Dear Mr. Richards:

On June 29, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2, facility. The enclosed inspection report documents the inspection results which were discussed on July 5, 2012, with Mr. G. Powell, Vice President, Generation, Units 1 and 2, and other members of your staff.

The inspections examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Two NRC-identified finding s of very low safety significance (Green) were identified during this inspection.

These finding s were determined to involve violation s of NRC requirements. Additionally, the NRC has determined that a traditional enforcement Severity Level IV violation occurred. This traditional enforcement violation was identified with an associated licensee

-identified violation

, which was determined to be of very low safety significance and is listed in this report. The NRC is treating these violation s as non-cited violation s (NCV s) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest any of these non-cited violation s , you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington

, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555

-0001; and the NRC Resident Inspector at the South Texas Project Electric Generating Station, Units 1 and 2, facility

. If you disagree with a cross

-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspector at the South Texas Project Electric Generating Station, Units 1 and 2, facility.

U N I T E D S T A T E S N U C L E A R R E G U L A T O R Y C O M M I S S I O N R E G I O N I V1600 EAST LAMAR BLVD A R L I N G T O N , T E X A S 7 6 0 1 1-4511 In accordance with 10 CFR 2.390 of the NRC

's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Wayne C. Walker , Branch Chief Project Branch A Division of Reactor Projects Docket Nos.: 50-498, 50-499 License No s.: NPF-76, NPF-80

Enclosure:

Inspection Report 05000 498/20 12 00 3 and 05000499/20 12 00 3

w/Attachment:

Supplemental Information cc w/encl: Electronic Distribution

SUMMARY OF FINDINGS

IR 05000 498/20 12003 , 05000499/20 12003; 03/31/2012

- 06/29/2012

South Texas Project Electric Generating Station, Units 1 and 2

, Integrated Resident and Regional Report;

Operability Evaluations and Functionality Assessments; Followup of Events

. The report covered a 3

-month period of inspection by resident inspectors and announced baseline inspections by region-based inspectors. Two Green and one Severity Level IV non-cited violations were identified.

The significance of most findings is indicated by their color (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609, "Significance Determination Process." The cross-cutting aspect is determined using Inspection Manual Chapter 0310, "Components Within the Cross-Cutting Areas." Findings for which the significance determination process does not apply may be Green or be assigned a severity level after NRC management review. The NRC

's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG

-1649, "Reactor Oversight Process," Revision 4, dated December 2006.

Cornerstone: Initiating Events

Severity Level IV. The inspectors identified a non-cited violation of 10 CFR 50.73(a)(2)(i)(B) for the failure to report a condition prohibited by technical specifications to the NRC within 60 days. Specifically, on March 6, 2012, after reviewing licensee records, the inspectors informed th e licensee that a violation of Technical Specification 3.4.1.4.2.b had occurred during the Unit 2 spring 2010 Refueling Outage 2RE13

, because valves which isolated an unborated water source were not locked in the closed position.

The licensee's corrective action included revising the reportability procedures to ensure that both units are addressed in the future.

The failure to report the occurrence of a condition prohibited by technical specifications is a performance deficiency which impacted the regulatory process and is a violation of NRC requirements. The violation was processed using traditional enforcement and determined to be a Severity Level IV violation consistent with Section 6.9 of the Enforcement Policy dated June 7, 2012 (Section 4OA3).

Cornerstone: Mitigating Systems

Green.

The inspectors identified a non-cited violation of 10 CFR 50.55a(g)(4) for the failure to follow in-service inspection requirements of Section XI of the 2004 ASME Boiler and Pressure Vessel Code. Specifically, the inspectors determined that the licensee had not correctly applied Section XI, IWA

-5250, to boric acid residues that were discovered under the base lip of the refueling water storage tank on September 20, 2011. The inspectors questioned the licensee's operability determination of fully operable and engineering disposition of "acceptable for use," because the degradation mechanism was not readily apparent and the licensee had not characterized the flaw. The licensee documented the issues in Condition Reports 12-20019 and 12

-20026 and changed the operability determination to operable but degraded

. This finding is more than minor because it affected the Mitigating Systems Cornerstone attribute of Design Control and affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences, and if left uncorrected it would have the potential to become a more significant safety concern because the structural integrity of the safety injection system's primary source of cooling water could be compromised.

The inspectors performed the significance determination using NRC Inspection Manual Chapter 0609, Attachment 0609.04, "Phase 1 - Initial Screening and Characterization of Findings," dated January 10, 2008, because it affected the Mitigating Systems Cornerstone while the plant was at power. The finding was determined to be of very low safety significance because it was not a design or qualification deficiency; it did not result in the loss of a system safety function; it did not represent a loss of a single train for greater than technical specification allowed outage time; it did not represent a loss of one or more nontechnical specification risk-significant equipment for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and it did not screen as potentially risk significant due to seismic, flooding, or severe weather.

In addition, this finding had a human performance cross-cutting aspect associated with decision making because the licensee did not make safety-significant decisions using a systematic process, especially when faced with uncertain or unexpected plant conditions, to ensure safety is maintained

H.1(a) (Section 1R15.1).

Cornerstone: Barrier Integrity

Green.

The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, for the failure to promptly identify condition s adverse to quality. Specifically, on May 21, 2012, the inspectors observed water was dripping from the isolation valve cubicle roof at several drops per minute and informed Unit 1 and 2 operations personnel to investigate further.

The licensee confirmed that train C and D steam generator power operated relief valves in each unit were leaking steam directly to the atmosphere

. The licensee entered the conditions into the corrective action program and plans to repair the valves at the next available opportunity.

The finding is more than minor because it is associated with the Barrier Integrity Cornerstone attribute of barrier performance and affected the cornerstone objective to protect the public from radionuclide releases caused by accidents or events because steam generator tube leakage events would release radionuclides directly to the atmosphere. The inspectors performed the significance determination using NRC Inspection Manual Chapter 0609,

Appendix HProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 0609,</br></br>Appendix H" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., dated May 6, 2004. The finding was determined to be of very low safety significance because it did not affect core damage frequency and the components involved were not identified as being important to large early release frequency. In addition, this finding ha s a human performance cross-cutting aspect associated with decision making because the licensee did not use conservative assumptions and adopt a requirement to demonstrate that the proposed action is safe in order to proceed H.1(b) (Section 1R15.2).

B. Licensee-Identified Violations

A violation of very low safety significance that was identified by the licensee has been reviewed by the inspectors. Corrective actions taken or planned by the licensee have been entered into the licensee's corrective action program. This violation and the associated corrective action tracking numbers are listed in Section 4OA7 of this report

.

REPORT DETAILS

Summary of Plant Status Unit 1 began the inspection period at 70 percent power as a result of restoring the plant from dropped shutdown rod M

-14. Unit 1 achieved 100 percent power on March 31, 2012, and remained there for the duration of the inspection period. Unit 2 began the inspection period in Mode 5, cold shutdown, in Forced Outage 2F1102 as a result of a main generator ground which caused a turbine trip and reactor trip on November 29, 2011, and remained there until April 21, 2012, when the unit went critical and entered Mode 1. On April 22, 2012 , the main generator output breaker was closed and power escalation began. Unit 2 reached 100 percent power on April 24, 2012, and remained there for the duration of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Summer Readiness for Offsite and Alternate

-AC Power a. The inspectors performed a review of preparations for summer weather for selected systems, including conditions that could lead to loss

-of-offsite power and conditions that could result from high temperatures. The inspectors reviewed the procedures affecting these areas and the communications protocols between the transmission system operator and the plant to verify that the appropriate information was being exchanged when issues arose that could affect the offsite power system. Examples of aspects considered in the inspectors' review included:

Inspection Scope The coordination between the transmission system operator and the plant

's operations personnel during off

-normal or emergency events The explanations for the events The estimates of when the offsite power system would be returned to a normal state The notifications from the transmission system operator to the plant when the offsite power system was returned to normal During the inspection, the inspectors focused on plant

-specific design features and the procedures used by plant personnel to mitigate or respond to adverse weather conditions. Additionally, the inspectors reviewed the UFSAR and performance requirements for systems selected for inspection

, and verified that operator actions were appropriate as specified by plant

-specific procedures. Specific documents reviewed during this inspection are listed in the attachment. The inspectors also reviewed corrective action program items to verify that the licensee was identifying adverse weather issues at an appropriate threshold and entering them into their corrective action program in accordance with station corrective action procedures.

The inspectors' reviews focused specifically on the following plant systems:

June 12, 2012, Units 1 and 2, standby

, auxiliary and emergency transformers

, engineered safety features transformers , and standby diesel generators These activities constitute completion of one readiness for summer weather affect on offsite and alternate

-ac power sample as defined in Inspection Procedure 71111.01-05. b. No findings were identified.

Findings

1R04 Equipment Alignments

.1 Partial Walkdown

a. The inspectors performed partial system walkdowns of the following risk

-significant systems: Inspection Scope April 5-6, 2012, Unit 2, spent fuel pool cooling and cleanup system train A April 5-6, 2012, Unit 2, spent fuel pool cooling and cleanup system train B The inspectors selected these systems based on their risk significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors attempted to identify any discrepancies that could affect the function of the system, and, therefore, potentially increase risk. The inspectors reviewed applicable operating procedures, system diagrams, UFSAR, technical specification requirements, administrative technical specification s, outstanding work orders, condition reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have rendered the systems incapable of performing their intended functions. The inspectors also inspected accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no obvious deficiencies. The inspectors also verified that the licensee had properly identified and resolved equipment alignment problems that could cause initiating events or impact the capability of mitigating systems or barriers and entered them into the corrective action program with the appropriate significance characterization. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of two partial system walkdown sample s as defined in Inspection Procedure 71111.04-05.

b. No findings were identified.

Findings

.2 Complete Walkdown

a. On June 27, 2012, the inspectors performed a complete system alignment inspection of the Unit 2 standby diesel generator 21 to verify the functional capability of the system. The inspectors selected this system because it was considered both safety significant and risk significant in the licensee's probabilistic risk assessment. The inspectors inspected the system to review mechanical and electrical equipment line ups, electrical power availability, system pressure and temperature indications, as appropriate, component labeling, component lubrication, component and equipment cooling, hangers and supports, operability of support systems, and to ensure that ancillary equipment or debris did not interfere with equipment operation. The inspectors reviewed a sample of past and outstanding work orders to determine whether any deficiencies significantly affected the system function. In addition, the inspectors reviewed the corrective action program database to ensure that system equipment

-alignment problems were being identified and appropriately resolved. Specific documents reviewed during this inspection are listed in the attachment.

Inspection Scope These activities constitute completion of one complete system walkdown sample as defined in Inspection Procedure 71111.04-05. b. No findings were identified.

Findings

1R05 Fire Protection

Quarterly Fire Inspection Tours a. The inspectors conducted fire protection walkdowns that were focused on availability, accessibility, and the condition of firefighting equipment in the following risk

-significant plant areas:

Inspection Scope April 21, 2012, Unit 2, cable area train A

, Fire Zone Z025 April 23, 2012, Unit 1, cable area train A

, Fire Zone Z025 April 23, 2012, Unit 2, cable area train B

, Fire Zone Z018 April 24, 2012, Unit 1, cable area train B

, Fire Zone Z018 The inspectors reviewed areas to assess if licensee personnel had implemented a fire protection program that adequately controlled combustibles and ignition sources within the plant; effectively maintained fire detection and suppression capability; maintained passive fire protection features in good material condition; and had implemented adequate compensatory measures for out of service, degraded or inoperable fire protection equipment, systems, or features, in accordance with the licensee's fire plan.

The inspectors selected fire areas based on their overall contribution to internal fire risk as documented in the plant's Individual Plant Examination of External Events with later additional insights, their potential to affect equipment that could initiate or mitigate a plant transient, or their impact on the plant's ability to respond to a security event. Using the documents listed in the attachment, the inspectors verified that fire hoses and extinguishers were in their designated locations and available for immediate use; that fire detectors and sprinklers were unobstructed

that transient material loading was within the analyzed limits; and fire doors, dampers, and penetration seals appeared to be in satisfactory condition. The inspectors also verified that minor issues identified during the inspection were entered into the licensee's corrective action program. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of four quarterly fire

-protection inspection sample s as defined in Inspection Procedure 71111.05-05. b. No findings were identified.

Findings

1R06 Flood Protection Measures

a. The inspectors reviewed the UFSAR, the flooding analysis, and plant procedures to assess susceptibilities involving internal flooding; reviewed the corrective action program to determine if licensee personnel identified and corrected flooding problems; inspected underground bunkers/manholes to verify the adequacy of sump pumps, level alarm circuits, cable splices subject to submergence, and drainage for bunkers/manholes; and verified that operator actions for coping with flooding can reasonably achieve the desired outcomes. The inspectors also inspected the areas listed below to verify the adequacy of equipment seals located below the flood line, floor and wall penetration seals, watertight door seals, common drain lines and sumps, sump pumps, level alarms, and control circuits, and temporary or removable flood barriers. Specific documents reviewed during this inspection are listed in the attachment.

Inspection Scope April 18, 2012, Units 1 and 2, spent fuel pool cooling pump and heat exchanger rooms April 23, 2012, Units 1 and 2, safety

-related electrical cable vault manhole inspections These activities constitute completion of one flood protection measures inspection sample and one bunker/manhole sample as defined in Inspection Procedure 71111.06-05. b. No findings were identified.

Findings

1R07 Heat Sink Performance

a. The inspectors reviewed licensee programs to verify heat exchanger performance and operability for the following heat exchangers:

Inspection Scope Unit 1, residual heat removal heat exchanger train A Unit 1, component cooling water heat exchanger train A Unit 2, emergency diesel generator 22 cooling water system train A Unit 2, essential chiller train B The inspectors verified whether testing, inspection, maintenance, and chemistry control programs were adequate to ensure proper heat transfer. The inspectors verified that the periodic testing and monitoring methods, as outlined in commitments to NRC Generic Letter 89-13, utilized proper industry heat exchanger guidance. Additionally, the inspectors verified that the licensee's chemistry program ensured that biological fouling was properly controlled between tests. The inspectors reviewed previous maintenance records of the heat exchangers to verify that the licensee's heat exchanger inspections adequately addressed structural integrity and cleanliness of their tubes. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of four triennial heat sink inspection samples as defined in Inspection Procedure 71111.07-05. b. No findings were identified.

Findings

1R11 Licensed Operator Requalification Program and Licensed Operator Performance

.1 Quarterly Review of Licensed Operator Requalification Prog

r am a. On May 24, 2012, the inspectors observed a crew of licensed operators in the plant's simulator during training. The inspectors assessed the following areas:

Inspection Scope Licensed operator performance The quality of the training provided The modeling and performance of the control room simulator Foll ow-up actions taken by the licensee for identified discrepancies These activities constitute completion of one quarterly licensed

-operator requalification program sample as defined in Inspection Procedure 71111.11.

b. No findings were identified.

Findings

.2 Quarterly Observation of Licensed Operator Performance

a. Inspection Scope

From April 20

-21, 2012, the inspectors observed the performance of on

-shift licensed operators in the plant's Unit 2 main control room. At the time of the observations, the plant was in a period of heightened activity and risk due to plant heat up to normal operating temperature and pressure, reactor startup, and closing the main generator output breaker following Forced Outage 2F1102. In addition, the inspectors assessed the operators' adherence to plant procedures, including conduct of operations procedure and other operations department policies.

These activities constitute completion of one quarterly licensed

-operator performance sample as defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

1R12 Maintenance Effectiveness

a. The inspectors evaluated degraded performance issues involving the following risk-significant systems:

Inspection Scope June 15, 2012, engineered safety features actuation system The inspectors reviewed events such as where ineffective equipment maintenance has resulted in valid or invalid automatic actuations of engineered safeguards systems and independently verified the licensee

's actions to address system performance or condition problems in terms of the following:

Implementing appropriate work practices Identifying and addressing common cause failures Scoping of systems in accordance with 10 CFR 50.65(b)

Characterizing system reliability issues for performance Charging unavailability for performance Trending key parameters for condition monitoring Ensuring proper classification in accordance with 10 CFR 50.65(a)(1) or (a)(2)

Verifying appropriate performance criteria for structures, systems, and components classified as having an adequate demonstration of performance through preventive maintenance, as described in 10 CFR 50.65(a)(2), or as requiring the establishment of appropriate and adequate goals and corrective actions for systems classified as not having adequate performance, as described in 10 CFR 50.65(a)(1)

The inspectors assessed performance issues with respect to the reliability, availability, and condition monitoring of the system. In addition, the inspectors verified maintenance effectiveness issues were entered into the corrective action program with the appropriate significance characterization. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of one quarterly maintenance effectiveness sampl e as defined in Inspection Procedure 71111.12-05. b. No findings were identified.

Findings

1R13 Maintenance Risk Assessments and Emergent Work Control

a. The inspectors reviewed licensee personnel

's evaluation and management of plant risk for the maintenance and emergent work activities affecting risk-significant and safety-related equipment listed below to verify that the appropriate risk assessments were performed prior to removing equipment for work:

Inspection Scope March 3-April 22, 2012, Unit 2, activities associated with Forced Outage 2F1102, including multiple residual heat removal pump rotations

, heatup , startup , and main generator breaker closure April 29-May 5, 2012, Unit 1, train A medium risk work activity on qualified display processing system; essential cooling water system and essential chiller 12A maintenance; and Unit 2, train D planned maintenance June 25-29, 2012, Unit 2, emergent, medium risk work activity on reactor coolant system hot leg temperature indication and train D planned maintenance The inspectors selected these activities based on potential risk significance relative to the reactor safety cornerstones. As applicable for each activity, the inspectors verified that licensee personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When licensee personnel performed emergent work, the inspectors verified that the licensee personnel promptly assessed and managed plant risk. The inspectors reviewed the scope of maintenance work, discussed the results of the assessment with the licensee

's probabilistic risk analyst or shift technical advisor, and verified plant conditions were consistent with the risk assessment. The inspectors also reviewed the technical specification requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid and applicable requirements were met. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of three maintenance risk assessments and emergent work control inspection sample s as defined in Inspection Procedure 71111.13-05. b. No findings were identified.

Findings

1R15 Operability Evaluations and Functionality Assessments

a. The inspectors reviewed the following assessments

Inspection Scope April 18, 2012, Unit 2, safety injection check valve SI

-10A, seal cap enclosure leaking and bolted joint integrity May 21, 2012, Unit 1 and 2, steam leakage past train C and D steam generator power operated relief valves June 14, 2012, Unit 1, safety injection system refueling water storage tank (RWST) flaw indicati ons The inspectors selected these operability and functionality assessments based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the evaluations to ensure technical specification operability was properly justified and to verify the subject component or system remained available such that no unrecognized increase in risk occurred. The inspectors compared the operability and design criteria in the appropriate sections of the technical specifications and UFSAR to the licensee's evaluations to determine whether the components or systems were operable. Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were properly controlled. Additionally, the inspectors reviewed a sampling of corrective action documents to verify that the licensee was identifying and correcting any deficiencies associated with operability evaluations. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of three operability evaluations inspection samples as defined in Inspection Procedure 71111.15-05.

b.

===.1

=

The inspectors identifi ed a non-cited violation of 10 CFR 50.55a(g)(4) for the failure to follow in

-service inspection requirements of Section XI of the 2004 ASME Boiler and Pressure Vessel Code. Specifically, the inspectors determined that the licensee had not correctly applied the ASME Code,Section XI, IWA

-5250, to boric acid residues that were discovered under the base lip of the RWST on September 20, 2011. The inspectors questioned the licensee's operability determination of fully operable and engineering disposition of "acceptable for use," because the degradation mechanism was not readily apparent and the licensee had not characterized the flaw.

Findings

Description.

On September 20, 2011, boric acid residues were discovered under the base lip of the Unit 1 RWST in two locations near the RWST discharge line. The residues were indicative of a leak from the tank. The RWST is the primary source of borated water for the safety injection system. Upon discovery of the condition, operations personnel requested an engineering evaluation to determine if the RWST remained operable.

Engineering staff completed a material deficiency evaluation instead of a prompt operability determination evaluation and recommended that the RWST was degraded but acceptable for use. However, operations personnel determined that the RWST was fully operable instead of operable but degraded, which would have classified the condition as an NRC Regulatory Issue Summary 2005

-20 issue and scheduled repairs at the next available opportunity. The licensee based their conclusion on a previous analysis that bounded a flaw from a separate leak on the opposite side of the tank that the licensee has been monitoring since 1997. The 1997 leak was from a flaw on the base lip of the RWST. The inspectors reviewed the evaluation and toured the RWST to observe the condition. The inspectors determined that the evaluation was not applicable to the current condition because the boric acid residues were under the base lip of the RWST and the stress analysis was performed for a crack on the base lip of the tank. The inspectors also questioned the validity of the licensee's original stress analysis and conclusion that the tank was fully operable

. The inspectors also notified the licensee that 10 CFR 50.55a(g)(4) requires the licensee to implement Section XI of the ASME Boiler and Pressure Vessel Code of record (ASME Code). The South Texas Project ASME Code of record is the 2004 edition. The inspectors reviewed Section XI of the 2004 ASME Code for applicability and determined that the licensee was responsible for implementing repairs to the tank to restore the tank to the original design as noted in Section III of the ASME Code.

Section XI, IWA-5250 , "Corrective Actions

," requires that when boric acid residues are detected on components, the leakage source and the areas of general corrosion shall be located. Since the residues appeared to originate from under the base lip of the tank, the licensee could not immediately locate the source of the potential corrosion. Additionally, the licensee's original evaluation had not considered that the RWST was susceptible to general corrosion because it was made from type 30 4 stainless steel.

The inspectors questioned the licensee's actions to defer locating and evaluating the leakage source because it was not in compliance with the code.

After further review, the licensee acknowledged that the condition of the RWST was not correctly dispositioned. Therefore, instead of requesting the approval to use an alternative method from the NRC, the licensee chose to invoke ASME Code Case N-705, "Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks," and revise the prompt operability determination. The evaluation concluded the tank was operable but degraded and should be repaired at the next available opportunity.

The licensee also performed a common cause analysis to determine why the ASME Code was not correctly applied to this condition.

The licensee documented corrective actions for the inadequate evaluation and failure to implement the ASME C od e in Condition Reports 12

-20019 and 12-20026. The licensee plans to repair the RWST during the fall outage and develop a systematic process for consistently implementing the ASME Code requirements.

Analysis.

The failure to follow ASME Code requirements is a performance deficiency. This finding was more than minor because it affected the Mitigating Systems Cornerstone attribute of Design Control and affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences, and if left uncorrected it would have the potential to become a more significant safety concern because the structural integrity of the safety injection system's primary source of cooling water could be compromised.

The inspectors performed the significance determination using NRC Inspection Manual Chapter 0609, Attachment 0609.04, "Phase 1

- Initial Screening and Characterization of Findings," dated January 10, 2008, because it affected the Mitigating Systems Cornerstone while the plant was at power. The finding was determined to be of very low safety significance because it was not a design or qualification deficiency; it did not result in the loss of a system safety function; it did not represent a loss of a single train for greater than technical specification allowed outage time; it did not represent a loss of one or more nontechnical specification ri sk-significant equipment for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and it did not screen as potentially risk significant due to seismic, flooding, or severe weather.

In addition, this finding had a human performance cross

-cutting aspect associated with decision making because the licensee did not make safety-significant decisions using a systematic process, especially when faced with uncertain or unexpected plant conditions, to ensure safety is maintained H.1(a). Enforcement

. Title 10 of the Code of Federal Regulation s, Part 50.55 a(g)(4) requires, in part, that components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in Section XI of editions and addenda of the ASME Boiler and Pressure Vessel Code. Contrary to the above, on September 20, 2011, the licensee failed to ensure that the RWST, a Class 2 component, met the requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code. Since this violation was of very low safety significance and was documented in the licensee's corrective action program as Condition Reports 11

-17459, 11-23915, 12-20019, and 12-20026, it is being treated as a non

-cited violation consistent with Section 2.3

.2 of the NRC Enforcement Policy:

NCV 05000498/2012003

-01, "Failure to Follow ASME Code Requirements

."

===.2

=

The inspectors identified a non

-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, for the failure to promptly identify conditions adverse to quality - steam leakage from Unit 1 and 2 train C and D steam generator power operated relief valves. The licensee entered the condition into the corrective action program for repair at the next available opportunity.

Description.

On May 21, 2012, the inspectors notified the Unit 1 and Unit 2 operations shift managers that water was dripping from the isolation valve cubicle roof at several drops per minute and to investigate further. Operations personnel confirmed that train C and D steam generator power operated relief valves in each unit were leaking steam to the atmosphere, which was condensing and dripping water onto the ground.

Station Procedure 0PGP03

-ZX-0002, "Condition Reporting Process ," Revision 43, and operations Procedure 0POP01

-ZQ-0022, "Shift Routines," Revision 65, h ad requirements for initiating condition reports and corrective actions for deficiencies.

In general, all station personnel, and more specifically, operations personnel, are charged with the responsibility to identify deficiencies and enter them into the licensee's corrective action program for resolution. The inspectors determined it was reasonable for the licensee to have promptly identified the leakage from the steam generator power operated relief valves and entered the conditions into the corrective action program because there were multiple steam generator power operated relief valves on each unit, and the condition s were readily apparent in an area frequently traversed by station personnel.

Analysis.

The failure to promptly identify leakage from steam generator power operated relief valves is a performance deficiency. The finding is more than minor because it was associated with the Barrier Integrity Cornerstone attribute of barrier performance and affected the cornerstone objective to protect the public from radionuclide releases caused by accidents or events because steam generator tube leakage events would release radionuclides directly to the atmosphere. The inspectors performed the significance determination using NRC Inspection Manual Chapter 0609, Appendix H, dated May 6, 2004. The finding was determined to be of very low safety significance because it did not affect core damage frequency and the components involved were not identified as being important to large early release frequency. In addition, this finding had a human performance cross

-cutting aspect associated with decision making because the licensee did not use conservative assumptions and adopt a requirement to demonstrate that the proposed action is safe in order to proceed H.1(b).

Enforcement.

Title 10 of the Code of Federal Regulations

, Part 50 , Appendix B, Criterion XVI requires

, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. Contrary to the above, on May 21, 2012, the licensee failed to promptly identify a deficiency associated with the Unit 1 and Unit 2 train C and D steam generator power operated relief valves. Since this violation was of very low safety significance and was documented in the licensee's corrective action program as Condition Reports 12-24036, 12-21808, 12-21922, 12-21925, and 12

-21943, it is being treated as a non-cited violation consistent with Section 2.3.2 of the NRC Enforcement Policy:

NCV 05000498/2012003-02 and 05000499/2012003

-02, "Failure to Promptly Identify Condition s Adverse to Quality."

1R18 Plant Modifications

a. Inspection Scope

Permanent Modifications On June 21, 2012, the inspectors completed the review of key parameters associated with materials, replacement components, equipment protection from hazards, operations, flow paths, pressure boundary, ventilation boundary, structural, process medium properties, licensing basis, and failure modes for the permanent modification identified as the Unit 2 essential cooling water system self

-cleaning strainer 2B repair.

The inspectors verified that modification preparation, staging, and implementation did not impair emergency/abnormal operating procedure actions, key safety functions, or operator response to loss

-of-key safety functions; post

-modification testing will maintain the plant in a safe configuration during testing by verifying that unintended system interactions will not occur

systems, structures and components' performance characteristics still meet the design basis

the modification design assumptions were appropriate; the modification test acceptance criteria will be met; and licensee personnel identified and implemented appropriate corrective actions associated with permanent plant modifications. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of one sample for permanent plant modifications as defined in Inspection Procedure 71111.18-05. b. No findings were identified.

Findings

1R19 Post-maintenance Testing

a. The inspectors reviewed the following post

-maintenance activities to verify that procedures and test activities were adequate to ensure system operability and functional capability:

Inspection Scope April 12, 2012, Unit 1, essential chiller 12B relay and temperature switch replacements and motor oil replacement May 4, 2012, Unit 1, essential chiller 12A oil outlet high temperature switch replacement and pre

-rotation vane and hot gas bypass motor inspection May 31, 2012, Unit 1, replacement of train A safety

-related 125

-volt DC E1A11 battery breaker June 25, 2012, Unit 2, standby diesel generator 22

, 5-year preventative maintenance activities The inspectors selected these activities based upon the structure, system, or component's ability to affect risk. The inspectors evaluated these activities for the following (as applicable):

The effect of testing on the plant had been adequately addressed; testing was adequate for the maintenance performed Acceptance criteria were clear and demonstrated operational readiness; test instrumentation was appropriate The inspectors evaluated the activities against the technical specification s, the UFSAR , 10 CFR Part 50 requirements, licensee procedures, and various NRC generic communications to ensure that the test results adequately ensured that the equipment met the licensing basis and design requirements. In addition, the inspectors reviewed corrective action documents associated with post

-maintenance tests to determine whether the licensee was identifying problems and entering them in the corrective action program and that the problems were being corrected commensurate with their importance to safety. Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of four post-maintenance testing inspection samples as defined in Inspection Procedure 71111.19-05. b. No findings were identified.

Findings

1R20 Refueling and Other Outage Activities

a. The inspectors reviewed the outage safety plan and contingency plans for the Unit 2 Forced Outage 2F1102, conducted November 29, 2011 through April 22, 2012, to confirm that licensee personnel had appropriately considered risk, industry experience, and previous site

-specific problems in developing and implementing a plan that assured maintenance of defense in depth. During the forced outage to repair the main generator , the inspectors observed portions of the shutdown and cooldown processes and monitored licensee controls over the outage activities listed below.

Inspection Scope Configuration management, including maintenance of defense in depth, is commensurate with the outage safety plan for key safety functions and compliance with the applicable technical specification s when taking equipment out of service.

Clearance activities, including confirmation that tags were properly hung and equipment appropriately configured to safely support the work or testing.

Installation and configuration of reactor coolant pressure, level, and temperature instruments to provide accurate indication, accounting for instrument error.

Status and configuration of electrical systems to ensure that technical specification s and outage safety

-plan requirements were met, and controls over switchyard activities.

Monitoring of decay heat removal processes, systems, and components.

Reactor water inventory controls, including flow paths, configurations, and alternative means for inventory addition, and controls to prevent inventory loss.

Controls over activities that could affect reactivity.

Startup and ascension to full power operation, tracking of startup prerequisites, walkdown of the drywell (primary containment) to verify that debris had not been left which could block emergency core cooling system suction strainers, and reactor physics testing.

Licensee identification and resolution of problems related to refueling outage activities.

Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of one refueling outage and other outage inspection sample as defined in Inspection Procedure 71111.20-05. b. No findings were identified.

Findings

1R22 Surveillance Testing

a. The inspectors reviewed the UFSAR, procedure requirements, and technical specifications to ensure that the surveillance activities listed below demonstrated that the systems, structures, and/or components tested were capable of performing their intended safety functions. The inspectors either witnessed or reviewed test data to verify that the significant surveillance test attributes were adequate to address the following:

Inspection Scope Preconditioning Evaluation of testing impact on the plant Acceptance criteria Test equipment Procedures Jumper/lifted lead controls Test data Testing frequency and method demonstrated technical specification operability Test equipment removal Restoration of plant systems Fulfillment of ASME Code requirements Updating of performance indicator data Engineering evaluations, root causes, and bases for returning tested systems, structures, and component s not meeting the test acceptance criteria were correct Reference setting data Annunciators and alarms setpoints The inspectors also verified that licensee personnel identified and implemented any needed corrective actions associated with the surveillance testing.

April 2, 2012, Unit 1, monthly control rod operability surveillance testing , and increased rod exercising on shutdown bank A rod M

-14 due to marginal traces April 19, 2012, Unit 2, digital rod position indication operability test May 11, 2012, Unit 2, train A engineered safety features load sequencer manual local test June 4, 2012, Unit 2, reactor coolant system leakage detection following Forced Outage 2F1102 June 16, 2012, Unit 1, essential chill water pump 11C inservice test June 29, 2012, Unit 2, reactor coolant system hot leg channel TI

-430A failure

, and placement of loop C hot leg channel 430 in two thermocouple operation Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of six surveillance testing inspection samples as defined in Inspection Procedure 71111.22-05.

b. No findings were identified.

Findings Cornerstone: Emergency Preparedness

1EP1 Exercise Evaluation

a. The licensee submitted the preliminary exercise scenario on March 9, 2012, as required by Appendix E to 10 CFR Part 50, Part IV.F.2.a. The inspectors performed an in

-office review of the scenario and objectives to determine if the proposed exercise acceptably tested major elements of the license e's emergency plan, allowed for demonstration of key emergency preparedness skills, provided a challenging drill environment, avoided the preconditioning of participant responses, and supported the exercise evaluation objectives.

Inspection Scope The inspectors observed the emergency plan exercise conducted May 9, 2012, to determine if the exercise tested major elements of the licensee's emergency plan, allowed for demonstration of key emergency preparedness skills, and avoided preconditioning participant responses. The scenario events were designed to escalate through the emergency classifications from an Alert to a General Emergency classification to demonstrate licensee personnel's capability to implement their emergency plan. The scenario simulated the following:

Defective nuclear fuel A breaker explosion affecting fuel pool cooling A leak on a letdown heat exchanger Loss-of-one train of essential equipment cooling water Loss-of-offsite power to a vital electrical bus A large break in the reactor coolant system leading to reactor vessel water level below top of active fuel Cold leg recirculation from the containment sump An unisolable leak outside containment causing a radioactive release to the environment The inspectors evaluated exercise performance by focusing on the risk

-significant activities of event classification, offsite notification, recognition of offsite dose consequences, and development of protective action recommendations in the control room simulator and the following dedicated emergency response facilities:

Technical Support Center Operations Support Center Emergency Operations Facility The inspectors also assessed recognition of, and response to, abnormal and emergency plant conditions

the transfer of decision

-making authority and emergency function responsibilities between facilities

onsite and offsite communications

protection of emergency workers

emergency repair evaluation and capability

and the overall implementation of the emergency plan to protect public health and safety and the environment. The inspectors reviewed the current revision of the facility emergency plan, emergency plan implementing procedures associated with operation of the licensee's emergency response facilities, procedures for the performance of associated emergency functions, and other documents as listed in the attachment to this report.

The inspectors compared the observed exercise performance with the requirements in the facility emergency plan, 10 CFR 50.47(b), 10 CFR Part 50, Appendix E, and with the guidance in the emergency plan implementing procedures and other federal guidance.

The inspectors attended the post

-exercise critiques in each emergency response facility to evaluate the initial licensee self

-assessment of exercise performance. The inspectors also attended a formal presentation of critique items to plant management conducted on May 30, 2012.

Specific documents reviewed during this inspection are listed in the attachment.

These activities constitute completion of one sample as defined in Inspection Procedure 71114.01-05. b. No findings were identified.

Findings

OTHER ACTIVITIES

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security

4OA1 Performance Indicator Verification

.1 Data Submission Issue

a. The inspectors performed a review of the performance indicator data submitted by the licensee for the first quarter 20 12 performance indicators for any obvious inconsistencies prior to its public release in accordance with Inspection Manual Chapter 0608, "Performance Indicator Program."

Inspection Scope This review was performed as part of the inspectors' normal plant status activities and, as such, did not constitute a separate inspection sample.

b. No findings were identified

. Findings

.2 Unplanned Scrams per 7000 Critical Hours

(IE01) a. The inspectors sampled licensee submittals for the unplanned scrams per 7000 critical hours performance indicator for Units 1 and 2 for the period from the second quarter 2011 through the first quarter 2012.

To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6. The inspectors reviewed the licensee's operator narrative logs, issue reports, event reports

, and NRC integrated inspection reports for the period of April 2011 through March 2012 to validate the accuracy of the submittals. The inspectors also reviewed the licensee's issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. Specific documents reviewed are described in the attachm ent to this report

. Inspection Scope These activities constitute completion of one unplanned scrams per 7000 critical hours sample per unit as defined in Inspection Procedure 71151-05. b. No findings were identified.

Findings

.3 Unplanned Power Changes per 7000 Critical Hours (IE03)

a. The inspectors sampled licensee submittals for the unplanned power changes per 7000 critical hours performance indicator for Units 1 and 2 for the period from the second quarter 2011 through the first quarter 2012.

To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6. The inspectors reviewed the licensee's operator narrative logs, issue reports, Maintenance Rule records, event reports

, and NRC integrated inspection reports for the period of April 2011 through March 2012 to validate the accuracy of the submittals. The inspectors also reviewed the licensee's issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. Specific documents reviewed are described in the attachment to this report

. Inspection Scope These activities constitute completion of one unplanned transient s per 7000 critical hours sample per unit as defined in Inspection Procedure 71151

-05.

b. No findings were identified.

Findings

.4 Unplanned Scrams with Complications

(IE0 4) a. The inspectors sampled licensee submittals for the unplanned scrams with complications performance indicator for Units 1 and 2 for the period from the second quarter 2011 through the first quarter 2012. To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision

6. The inspectors reviewed the licensee's operator narrative logs, issue reports, event reports

, and NRC integrated inspection reports for the period of April 2011 through March 2012 to validate the accuracy of the submittals. The inspectors also reviewed the licensee's issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. Specific documents reviewed are described in the attachment to this report

. Inspection Scope These activities constitute completion of one unplanned scrams with complications sample per unit as defined in Inspection Procedure 71151-05. b. No findings were identified.

Findings

.5 Drill/Exercise Performance

(EP01) a. The inspectors sampled licensee submittals for the drill/exercise performance performance indicator for the period July 2011 through March 2012. To determine the accuracy of the performance indicator data reported during those periods, performance indicator definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used. The inspectors reviewed the licensee's records associated with the performance indicator to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the performance indicator; assessments of performance indicator opportunities during predesignated control room simulator training sessions

performance during the 2012 biennial exercise

and performance during other drills. Specific documents reviewed are described in the attachme nt to this report

. Inspection Scope These activities constitute completion of the drill/exercise performance sample as defined in Inspection Procedure 71151-05.

b. No findings were identified.

Findings

.6 Emergency Response Organization Drill Participation

(EP02) a. The inspectors sampled licensee submittals for the emergency response organization drill participation performance indicator for the period July 2011 through March 2012. To determine the accuracy of the performance indicator data reported during those periods, performance indicator definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used. The inspectors reviewed the licensee's records associated with the performance indicator to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the performance indicator

rosters of personnel assigned to key emergency response organization positions

and exercise participation records. Specific documents reviewed are described in the attachment to this report

. Inspection Scope These activities constitute completion of the emergency response organization drill participation sample as defined in Inspection Procedure 71151-05. b. No findings were identified.

Findings

.7 Alert and Notification System

(EP03) a. The inspectors sampled licensee submittals for the alert and notification system performance indicator for the period July 2011 through March 2012. To determine the accuracy of the performance indicator data reported during those periods, performance indicator definitions and guidance contained in NEI Document 99

-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used. The inspectors reviewed the licensee's records associated with the performance indicator to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the performance indicator; and the results of periodic alert notification system operability tests. Specific documents reviewed are described in the attachment to this report

. Inspection Scope These activities constitute completion of the alert and notification system sample as defined in Inspection Procedure 71151-05.

b. No findings were identified.

Findings

4OA2 Problem Identification and Resolution

.1 Routine Review of Identification and Resolution of Problems

a. As part of the various baseline inspection procedures discussed in previous sections of this report, the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that they were being entered into the licensee's corrective action program at an appropriate threshold, that adequate attention was being given to timely corrective actions, and that adverse trends were identified and addressed. The inspectors reviewed attributes that included the complete and accurate identification of the problem; the timely correction, commensurate with the safety significance; the evaluation and disposition of performance issues, generic implications, common causes, contributing factors, root causes, extent of condition reviews, and previous occurrences reviews; and the classification, prioritization, focus, and timeliness of corrective actions. Minor issues entered into the licensee's corrective action program because of the inspectors' observations are included in the attached list of documents reviewed. Inspection Scope These routine reviews for the identification and resolution of problems did not constitute any additional inspection samples. Instead, by procedure, they were considered an integral part of the inspections performed during the quarter and documented in Section 1 of this report.

b. No findings were identified.

Findings

.2 Daily Corrective Action Program Reviews

a. In order to assist with the identification of repetitive equipment failures and specific human performance issues for followup, the inspectors performed a daily screening of items entered into the licensee's corrective action program. The inspectors accomplished this through review of the station's daily corrective action documents.

Inspection Scope The inspectors performed these daily reviews as part of their daily plant status monitoring activities and, as such, did not constitute any separate inspection samples.

b. No findings were identified.

Findings

.3 Semi-Annual Trend Review

a. The inspectors performed a review of the licensee's corrective action program and associated documents to identify trends that could indicate the existence of a more significant safety issue. The inspectors focused their review on repetitive equipment issues, but also considered the results of daily corrective action item screening discussed in Section 4OA2.2, above, licensee trending efforts, and licensee human performance results. The inspectors nominally considered the 6

-month period of January through June 2012, although some examples expanded beyond those dates where the scope of the trend warranted.

Inspection Scope The inspectors also included issues documented outside the normal corrective action program in major equipment problem lists, repetitive and/or rework maintenance lists, departmental problem/challenges lists, system health reports, quality assurance audit/surveillance reports, self

-assessment reports, and Maintenance Rule assessments. The inspectors compared and contrasted their results with the results contained in the licensee's corrective action program trending reports. Corrective actions associated with a sample of the issues identified in the licensee's trending reports were reviewed for adequacy. These activities constitute completion of one single semi

-annual trend inspection sample as defined in Inspection Procedure 71152-05. b. No findings were identified.

Findings

4OA3 Followup of Events and Notices of Enforcement

Discretion (71153) (Closed) Licensee Event Report (LER) 05000498/2011

-001, Revision 1, "Technical Specification Requirement Not Met Regarding Unborated Water Sources" On April 30, 2011, during Refueling Outage 1RE16, Unit 1 was in Mode 5 with the reactor coolant system loops not filled when the licensee identified that Technical Specification 3.4.1.4.2.b requirements were not met because an unborated source of water was not properly secured from the reactor coolant system. During the pre

-job review of a planned activity to transfer water from the boron recycle system recycle holdup tank 1B to the volume control tank, a senior reactor operator identified that two valves for the boron recycle system were not listed in the surveillance procedure used to ensure compliance with the technical specification. These valves, if left open, could have introduced unborated water from the demineralized water system into the reactor coolant system via the chemical volume and control system. The inspectors reviewed the root cause investigation, procedures, corrective action documents

, and interviewed station personnel. During this review, the inspectors identified that the same conditions occurred in Unit 2 within the last 3 years and were not reported by the licensee. The original licensee event report was closed in NRC Inspection Report 2012002. The licensee submitted Revision 1 of the LER to indicate that Unit 2 was also affected by this condition. The enforcement aspects of this finding are documented below and in Section 4OA7. This licensee event report is closed.

Introduction.

The inspectors identified a non

-cited violation of 10 CFR 50.73(a)(2)(i)(B) for the failure to report a condition prohibited by technical specifications to the NRC within 60 days. Specifically, on March 6, 2012, after reviewing licensee records, the inspectors informed the licensee that a violation of Technical Specification 3.4.1.4.2.b had occurred during the Unit 2 spring 2010 Refueling Outage 2RE13

, because valves which isolated an unborated water source were not locked in the closed position.

Description.

During the review of LER 05000498/2011

-001, Revision 0, the inspectors questioned the licensee about whether the condition applied to Unit 2

, and if an LER should have been submitted. Upon further review, the inspectors determined that control room logs from the 2010 Unit 2 outage indicated that the recycle holdup tank 2B as the source to refill reactor coolant system prior to restarting the unit. This indicated that the same line up as described in the LER for Unit 1 also occurred in Unit 2, and a violation of technical specification requirements had occurred (See Section

4OA7 for more on the

technical specification violation).

The licensee performed an investigation and determined that this was a knowledge based human error in which the wrong conclusion was reached. The licensee implemented corrective actions to change the reportability review guidance to consider if the other unit was affected and provided training to licensing personnel.

Analysis.

The failure to report the occurrence of a condition prohibited by technical specification s is a performance deficiency which impacted the regulatory process and was a violation of NRC requirements. The violation was processed using traditional enforcement and determined to be a Severity Level IV violation consistent with Section 6.9 of the Enforcement Policy dated June 7, 2012

. The finding was also processed using the significance determination process and is documented in Section 4OA7.

Enforcement.

Title 10 CFR 50.73(a)(2)(i)(B) requires, in part, that violations of technical specification s or condition s prohibited by technical specifications be reported to the NRC within 60 days. Contrary to the above, on July 11, 2011, the licensee submitted LER 050 00498/2011-001, Revision 0, without reporting that South Texas Project Unit 2 had also violated Technical Specification 3.4.1.4.2.b. Because this violation was entered in to the licensee's corrective action program as Condition Report 12-10874, it is being treated as a non-cited violation in accordance with Section 2.3.2 of the NRC Enforcement Policy: NCV 05000499/2012003

-003, "Failure to Report a Condition Prohibited by Technical Specifications."

4OA6 Meetings , Including Exit

Exit Meeting Summary

On March 23, 2012, the inspectors discussed the results of the in

-office review of the preliminary exercise scenario for the biennial emergency plan exercise with Mr. M. Keyes, Senior Emergency Preparedness Specialist. The licensee acknowledged the issues presented.

On May 24, 2012, the inspector s presented the final inspection results of the triennial heat sink inspection to Mr. G. Powell, Vice President, Generation, Units 1 and 2, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspector s asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

On June 4, 2012, the inspectors conducted a conference call to present the results of the onsite inspection of the licensee's biennial emergency plan exercise to Mr. D. Rencurrel, Chief Nuclear Officer, and other members of the licensee's staff. The licensee acknowledged the issues presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

On July 5, 2012, the inspectors presented the inspection results to Mr. G. Powell, Vice President, Generation, Units 1 and 2, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspector s asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

4OA7 Licensee-Identified Violations

The following violation of very low safety significance (Green) was identified by the licensee and is a violation of NRC requirements which meets the criteria of the NRC Enforcement Policy for being dispositioned as a non

-cited violation.

.1 Technical Specification 3.4.1.4.2.b requires that

when the reactor is in Mode 5 (cold shutdown) with reactor coolant system loops not filled, "each valve or mechanical joint used to isolate unborated water sources shall be secured in the closed position." Contrary to the above, every Unit 2 outage from 2003 through 2010, when the recycle holdup tanks were used to fill the reactor coolant system, boron recovery system valves BR

-204 and BR

-205 were closed but not secured (locked).

The inspectors used Manual Chapter 0609, Appendix G, and determined that the finding was of very low safety significance because there was no reactivity change that warranted a quantitative risk analysis. The licensee entered this violation into the corrective action program as Condition Report 11

-7747.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

R. Aguilera, Manager, Health Physics

M. Berg, Manager, Design Engineering

C. Bowman, General Manager, Engineering and Regulatory Affairs

D. Bryant, Manager, Chemistry

J. Calvert, Manager, Training

K. Coates, General Manager, Outages and Projects

R. Dunn Jr., Manager, Fuels and Analysis

R. Engen, Site Engineering Director

J. Enoch, Manager, Emergency Preparedness

T. Frawley, Manager, Operations

J. Hartley, Manager, Mechanical Maintenance

G. Hildebran

d t , Manager, EP/Plant Protection

G. Janak, Manager, Unit 1 Operations

B. Jenewein, Manager, Systems Engineering

J. Lovejoy, Manager, I&C Maintenance

G. MacDonald, Manager, Organizational Effectiveness

R. McNiel, Manager, Maintenance Engineering

J. Mertink, Plant Training and Knowledge Transfer

J. Milliff, Manager, Unit 2 Operations

M. Murray, Manager, Regulatory Affairs

J. Paul, Engineer, Licensing Consultant

L. Peter, Plant General Manager

J. Pierce, Manager, Operations Training

G. Powell, Vice President , Generation, Units 1 and 2

D. Rencurrel, Chief Nuclear Officer

K. Richards, President and Chief Executive Officer

M. Ruvalcaba, Manager, Testing and Programs

R. Rysner, Quality Department Staff

R. Savage, Engineer, Licensing Staff Specialist

M. Schaefer, Manager, Maintenance

S. Sovizral, Manager, Security Operations

D. Swett, Supervisor, Radiation Protection

K. Taplett, Senior Engineer, Licensing Staff

D. Towler, Manager, Quality

D. Tran, Quality Department Staff

J. Wells, Manager, Work Control/Outage

J. Wirths, Chemistry Staff

D. Zink, Supervising Engineering Specialist

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

05000498/2012003

-01 NCV Failure to Follow ASME Code Requirements (Section 1R15.1)

05000498/2012003-02

05000499/2012003

-02 NCV Failure to Promptly Identify Condition

s Adverse to Quality (Section 1R15

.2)

05000499/2012003

-03 NCV Failure to Report a Condition Prohibited by Technical Specifications (Section 4OA3)

05000498/2011001

-01 LER Technical Specification Requirement Not Met Regarding Unborated Water Sources Revision 1 (Section 4OA3)

Section 1R01: Adverse Weather Protection

CONDITION REPORTS

09-9556 12-5166 12-23163 12-23226 11-2638 12-14980

PROCEDURES

NUMBER TITLE REVISION

LOR-GL-0001 LOR Training Program Guidelines

0PGP03-XS-0001 Switchyard Management

0PGP03-ZA-0104 Switchyard Access and Control of Vehicles Near Electrical Power Components

0POP01-ZO-0002 345 kV Switchyard Switching and Clearance Guidelines

0POP03-ZG-0002 STP Coordinator Operations

0POP03-ZO-0045 Centerpoint Energy Real Time Operations Emergency Operations Plan

0POP04-AE-0004 Loss of Power to One or More 4.16 KV ESF Bus

0POP04-AE-0005 Offsite Power System Degraded

Section 1R04: Equipment Alignment

CONDITION REPORTS 12-9695 12-23388

DRAWINGS NUMBER TITLE REVISION 5R219F05028 #2

Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System

5R219F05029 #2

Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System

5Q159F22542 #2

Piping and Instrumentation Diagram Standby Diesel Lube Oil 19 5Q159F22540 #2

Piping and Instrumentation Diagram Standby Diesel Jacket Water

5Q159F00045 #2

Piping and Instrumentation Diagram Standby Diesel Fuel Oil 8 5Q159F22546 #2

Piping and Instrumentation Diagram Standby Diesel Starting Air

PROCEDURES

NUMBER TITLE REVISION 0POP02-FC-0001 Spent Fuel Pool Cooling and Cleanup System

0POP04-FC-0001 Loss of Spent Fuel Pool Level or Cooling

0POP02-DG-0001 Emergency Diesel Generator 11(21)

0PSP03-DG-0001 Standby Diesel Generator 11(21) Operability Test

Section 1R05: Fire Protection

CONDITION REPORTS

2-18509 12-12294 12-12465

FIRE PREPLANS

NUMBER TITLE REVISION 0EAB33-FP-0018 Fire Preplan Electrical Auxiliary Building Cable Area Train B 3 0EAB66-FP-0025 Fire Preplan Electrical Auxiliary Building Cabling Area Train A 2 PROCEDURES

NUMBER TITLE REVISION 0PTP03-FP-0126 Fire Door Visual Examination

0PTP03-FP-0127 Fire Door Hold Open and Release Mechanisms Functionality Check

17, 18

Section 1R06: Flood Protection Measures

CALCULATIONS

NUMBER TITLE REVISION MC5365 Fuel Handling Building Flooding Analysis

NC9708 Facility Response Analysis for FHB Flooding and Spray Effects

CONDITION REPORTS

11-11292 12-18726 12-19245 12-21160 12-16924

DRAWINGS NUMBER TITLE REVISION 5R219F05028#1

Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System

5R219F05028

1. 2 Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System 30 5R219F05029#1

Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System

5R219F05029#2

Piping and Instrumentation Diagram Spent Fuel Pool Cooling and Cleanup System

NUMBER TITLE REVISION 7F099A80471

Architectural Penetration Seals Fuel Handling Building Floor Plan El. (-)29'-0", (-) 2'-0", and 4'

-0" 4 7F099A80472

Architectural Penetration Seals Fuel Handling Building Floor Plan El. 21'

-11" and 30'

-0" 5 9F139A1048

Architectural Fuel Handling Building Plan @ 30'

-0" 3 3E100E02151

Electrical Class 1E Manhole Schedule and Details

3P110C5032

Concrete Class 1E Underground Electrical Raceway System Manhole Plan

3P110C5034

Concrete Class 1E Underground Electrical Raceway System General Plan

3P110C5035

Concrete Class 1E Underground Electrical Raceway System Manhole Plan

3E100E02153

Electrical Class 1E Manhole and Duct Bank Sections

3E100E02154

Electrical Class 1E Manhole and Duct Bank Sections

3E100E02155

Electrical Class 1E Manhole and Duct Bank Sections

3E100E02156

Electrical Class 1E Manhole and Duct Bank Sections

PROCEDURES

NUMBER TITLE REVISION 0POP02-FC-0001 Spent Fuel Pool Cooling and Cleanup System

WORK AUTHORIZATION NUMBERS

367583

390282 411949

Section 1R07: Heat Sink Performance

CALCULATIONS

NUMBER TITLE REVISION

MC 6084 Component Cooling Water Heat Exchanger Tube Plugging 0

MC 6219 Generic Letter 89

-13 (Essential Cooling Water Thermal Performance Test)

MC 6255 Standby Diesel Generator Intercooler Performance

NUMBER TITLE REVISION

MC 6476 Jacket Water and Lube Oil Cooler Performance

MC 6482 Essential Chiller Water/EAB HVAC Design Basis Loads

MC 6498 Essential Cooling Pond Thermal Performance Analysis

5R169MB01021

Residual Heat Removal System

- Design Basis Document

5R209MB1018

Component Cooling Water

- Design Basis Document

5Q159MB1023

Standby Diesel Generator System

5V369VB00120

Chilled Water System

- Design Basis Document

CONDITION REPORTS

09-10688 09-20886 11-25827 12-21568 09-17531 10-9232 11-31266 12-21573 09-19824 10-16495 12-9761 12-21625 09-20336 11-2695 12-21567 12-21934 09-20681 11-3194

HEAT EXCHANGER INSPECTION RESULTS PROCEDURES

NUMBER TITLE DATE 3Q152MHX0234

ESF Diesel Generator 22, Jacket Water Cooler Tube Scale Inspection April 25, 2006

3Q152MDG0234

ESF Diesel Generator 22, Intercooler Inspection April 25, 2006

100-02812-001

SDG 22 Lube Oil Cooler Tube Scale Inspection April 29, 2003

100-02813-002

SDG 22 Jacket Water Cooler Tube Scale Inspection April 29, 2003

MISCELLANEOUS

NUMBER TITLE REVISION/DATE

Stress Analysis for Component Cooling Water Heat Exchanger 0

Component Cooling Water System Water Hammer Effect on Residual Heat Exchanger System Components April 9, 1987

5Z010ZS1101

STP Precautions Limitations and Setpoints

ST-HL-AE-2400 Final Report Concerning Component Cooling Water Heat Exchanger November 5,1987

NUMBER TITLE REVISION/DATE

4018-01001-5C As-Built Information After Rodding and Plugging Component Cooling Water Heat Exchanger 1A

DCP 98-622-15 Design Change Package

- Standby Diesel Heat Exchanger Tube Plugging

DCP 04-14989-2 Tube Plugging for Essential Chillers April 4, 2005

WAN-92034253 Essential Cooler 22B Tube Cleaning and EDDY Current Testing 1 2 RH Residual Heat Removal System Health Report April 1, 2012

EW Essential Cooling Water System Health Report April 1, 2012

HC Containment HVAC System Health Report April 1, 2012

HM Mechanical Auxiliary Building HVAC System Health Report April 1, 2012

CC Component Cooling Water System Health Report April 1, 2012

CH Essential Chilled Water System Health Report April 1, 2012

2DG Standby Diesel Generator System Health Report April 1, 2012

AD-0020 Reactor Shutdown Chemistry Guidelines Chapter 11

Primary Chemistry Strategic Water Chemistry Plan Chapter 13

Closed Cooling water Chemistry Strategic Plan Chapter 14

Service (open Loop) Cooling Water Chemistry Strategic Plan 1 PROCEDURES

NUMBER TITLE REVISION 0PCP01-ZA-0038 Plant Chemistry Specification

0PCP03-ZC-0005 Chemistry Addition to the Reactor Coolant System 14 0PCP03-ZC-0006 Chemical Addition to Plant Systems

0PCP03-ZC-0013 Chemical Addition to CW/OC and EW

0PGP03-ZE-0080 Essential Cooling Water System Reliability Program

0PMP04-ZG-0011 Heat Exchanger Cleaning (general Guidelines and Instructions)

VENDOR DOCUMENTS

NUMBER TITLE REVISION/DATE

VTD-S445-0001 Installation Operation and maintenance Instructions for Cooling Water Heat Exchangers

VTD-W351-0005 Instruction manual for Westinghouse NSSS Heat Exchangers

DCP-95-5765-103 Revise Specification 3Q159MS0034

- for

SDG 22 Only

SDG Lube Oil Cooler Manufactures Design and Performance Data Sheet March 7, 1977

SDG Jacket Water Cooler Manufactures Design and Performance Data Sheet March 7, 1977

SDG Intercooler Manufactures Design and Performance Data Sheet June 28,1977

DCP-95-5765-8 Revise Specification 3Q159MS0034

- for

SDG 11 Only Essential Chiller Manufactures Data Sheet

WORK ORDERS

177923

272198

359443

401571

203951

277245

386797

402180

272197 353604

Section 1R11: Licensed Operator Requalification Program and Licensed Operator Performance

PROCEDURES

NUMBER TITLE REVISION 0POP02-RC-0003 Filling and Venting the Reactor Coolant System

0POP03-ZG-0001 Plant Heatup

0POP03-ZG-0004 Reactor Startup

Section 1R12: Maintenance Effectiveness

CONDITION REPORTS

99-2894 11-14081 12-2354 12-13302 11-13651 11-18562

MISCELLANEOUS

TITLE REVISION/DATE

ESF Load Sequencer Life Cycle Management Plan August 18, 2008

Integrated GQA/PGR Working Group Meeting May 16, 2012

Maintenance Rule System Scoping Basis Report March 8, 2012

Quarterly System Health Report ESF Actuation (SF)

Second Quarter 2010 through First Quarter 2012

Section 1R13: Maintenance Risk Assessment and Emergent Work Controls

CONDITION REPORTS 11-28753 12-12399 12-23404 12-23553 11-28904 12-21160

MISCELLANEOUS

TITLE REVISION/DATE STP RICTCAL and RASCAL Calculations April 29-May 5, 2012

Work Activity Risk Plan of Action #2369

0, 1 PROCEDURES

NUMBER TITLE REVISION 0PGP01-ZA-0304 Probabilistic Risk Assessment Risk Ranking

0PGP02-ZA-0003 Comprehensive Risk Management Program

0PGP03-ZA-0091 Configuration Risk Management Program

0PGP03-ZA-0101 Shutdown Risk Assessment

0PGP03-ZG-RMTS Risk-Managed Technical Specifications Program 1 0PGP03-ZO-0022 Post-Trip Review

0PMP07-AM-0011 QDPS

APC-A1 Removal From Service

0PMP07-AM-0022 QDPS

APC-B2 Removal From Service

0POP01-ZO-0006 Risk Management Actions (RMAs)

0POP02-RC-0003 Filling and Venting the Reactor Coolant System 36 0POP02-RH-0001 Residual Heat Removal System Operation

NUMBER TITLE REVISION 0POP03-ZG-0001 Plant Heatup

0POP03-ZG-0003 Secondary Plant Heatup

0POP03-ZG-0004 Reactor Startup

0POP03-ZG-0005 Plant Startup to 100%

0POP04-RP-0004 Failure of RCS Loop RTD Protection Channel

0POP07-RS-0001 Control Rod Exercise

0PSP03-XC-0002 Initial Containment Inspection to Establish Integrity

0PSP03-XC-0002A Containment Entry and Partial Inspection (Containment Integrity Established)

0PSP03-EW-0017 Essential Cooling Water System Train A Testing

WORK AUTHORIZATION NUMBERS

377238

400348

417958

450174 392818

Section 1R15: Operability Evaluations and Functionality Assessments

CONDITION REPORTS

97-5407 06-946 11-23915 12-21808 97-14680 06-10954 11-25873 12-21922 97-16031 06-15346 12-15564 12-21925 98-9447 07-6636 12-16203 12-21943 98-20193 09-3661 12-16493 12-23218 99-5317 11-11096 12-20019 12-23245 01-10038 11-11999 12-20026 12-23391 03-4528 11-17459 12-21063

DRAWINGS NUMBER TITLE REVISION/DATE 35199-1, -2 Drag

Valve, 8 x 10, Offset Globe, 900 ANSI Steam Generator Relief March 23, 2011

2400073 Body Assembly 8

" x 10" Globe Offset 900 ANSI CL

November 16, 1987

77-B110015-17 Flexcell 0 77-D110015 Refueling Water Storage Tank Vessel Data, Sheet 1

77-D110015 Refueling Water Storage Tank Orientation, Sheet 2

NUMBER TITLE REVISION/DATE 77-D110015 Refueling Water Storage Tank Bottom Layout, Sheet 3

77-D110015 Refueling Water Storage Tank Shell Stretchout Sheet 6

MISCELLANEOUS

NUMBER TITLE DATE N-513-2 Cases of ASME Boiler and Pressure Vessel Code - Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 February 20, 2004

UTCAL -2012-027 Safety Injection Valve SI0010A / Studs (16 each)

April 16, 2012

UT-2012-049 Safety Injection Valve SI0010A / Studs (16 each)

April 17, 2012

Case N-705 Cases of ASME Boiler and Pressure Vessel Code:

Case N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks,Section XI, Division 1

October 12, 2006

PROCEDURES

NUMBER TITLE REVISION

UTI-025 Ultrasonic Technical Instruction Manual Ultrasonic Examination of Threaded Bolting

0POP02-MS-0001 Main Steam System

0PSP03-MS-0001 Main Steam System Valve Operability Test

38-40 0PSP15-SI-0001 Safety Injection System Functional Pressure Test

0POP01-ZQ-0022 Plant Operations Shift Routines

Section 1R18: Plant Modifications

CONDITION REPORTS

2-21559 12-23125

DRAWINGS NUMBER TITLE REVISION/DATE

4056-01027ZU Strainer Assembly February 5, 2009

NUMBER TITLE REVISION/DATE

8056-01027ZU Strainer Assembly February 5, 2009

3R289NS0036

Essential Cooling Water System Self Cleaning Strainer

5R289F05038#2

Piping and Instrumentation Diagram Essential Cooling Water System 16 PROCEDURES

NUMBER TITLE REVISION 0PDP01-ZE-0001 Design Verification Process

0PGP03-ZA-0014 Foreign Materials Exclusion Program

0PGP04-ZE-0309 Design Change Package

0PGP05-ZA-0002 10CFR50.59 Evaluations

WORK AUTHORIZATION NUMBERS

443862

Section 1R19:

Post

-maintenance Testing

CONDITION REPORTS

11-23281 12-21519 12-21573 12-21782 12-15398 12-21559 12-21580 12-21882 12-15541 12-21560 12-21625 12-21908 12-19696 12-21562 12-21732 12-22116 12-20212 12-21568 12-21780 12-22243 PROCEDURES

NUMBER TITLE REVISION 0PMP05-CH-0003 York Chiller Inspection & Maintenance 300 Tons

0PMP05-NZ-0030 General Electric Type AKR Breaker Test

0PMP05-NZ-0035 Calibration of AKR Breaker Trip Devices

0PMP05-ZE-0047 Calibration of Timing Relays 12 0PMP05-ZE-0108 Type AR Auxiliary Relay

- Maintenance

0PMP08-ZI-0009 Pressure or Differential Pressure Switch Calibration

0PMP08-ZI-0203 Pressure or Differential Pressure Indicator Calibration

NUMBER TITLE REVISION 0PSP03-EW-0017 Essential Cooling Water System Train A Testing

WORK AUTHORIZATION NUMBERS

2285

400348

417958

443857

392818

404956

430494

442143

397143

411113

433066 442192

Section 1R20: Refueling and Other Outage Activities

CONDITION REPORTS

11-28753 11-28904 11-29195 12-12399 11-28754

PROCEDURES

NUMBER TITLE REVISION 0PGP03-ZA-0101 Shutdown Risk Assessment

0PGP03-ZO-0022 Post-Trip Review

0POP02-RC-0003 Filling and Venting the Reactor Coolant System

0POP02-RH-0001 Residual Heat Removal System Operation

0POP03-ZG-0001 Plant Heatup

0POP03-ZG-0003 Secondary Plant Heatup

0POP03-ZG-0004 Reactor Startup

0POP03-ZG-0005 Plant Startup to 100%

0POP03-ZG-0007 Plant Cooldown

0POP05-EO-E001 Reactor Trip Response

0POP07-RS-0001 Control Rod Exercise 9 0PSP03-XC-0002 Initial Containment Inspection to Establish Integrity

0PSP03-XC-0002A Containment Entry and Partial Inspection (Containment Integrity Established)

0POP02-DG-0002 Emergency Diesel Generator 12(22)

0PSP03-DG-0002 Standby Diesel 12(22) Operability Test

Section 1R22: Surveillance Testing

CONDITION REPORTS

2-9703 12-17138 12-17369 12-22543 12-13560 12-17232 12-18545 12-22787 12-13561 12-17340 12-18976 12-23035 12-13673 12-17342 12-21391 12-23404 12-16895 12-17368 12-22490 12-23553 PROCEDURES

NUMBER TITLE REVISION 0PGP03-ZO-0046 RCS Leakage Monitoring

0PGP07-ZA-0014 Software Quality Assurance Program

0PMP07-AM-0022 QDPS

APC-B2 Removal From Service

0POP04-RC-0003 Excessive RCS Leakage

0POP04-RP-0004 Failure of RCS Loop RTD Protection Channel

0POP04-RS-0001 Control Rod Malfunction

0POP07-RS-0001 Control Rod Exercise

0PSP02-RC-0410 Delta T and T Average ACOT

0PSP03-CH-0010 Essential Chilled Water Pump 11C(21C) Preservice Testing Pump Curve Measurement

0PSP03-RC-0006 Reactor Coolant Inventory

0PSP03-RC-0006A Alternate Reactor Coolant Inventory

0PSP03-RI-0001 Digital Rod Position Indication Operability Test

0PSP03-RS-0001 Monthly Control Rod Operability

0PSP03-RS-0004 Control Rod Operability Test (Six and Ten Steps)

0PSP03-SP-0010A Train A ESF Load Sequencer Manual Local Test

1TOP02-RS-0003 Rod Exercise (M14, P4, F12, F2, N11, N5, K2, L13, E3, L3, K14) 6 WORK AUTHORIZATION NUMBERS

416148

422992

442759

450174

421144

434346 449161

Section 1EP1: Exercise Evaluation

CONDITION REPORTS

2-21330 12-21524 12-22275 12-22282 12-21349 12-21696 12-22281

MISCELLANEOUS

TITLE DATE Evaluation Report for the Red Team Drill, January 27, 2010

May 6, 2010

Evaluation Report for the Blue Team Drill, May 26, 2010

October 10, 2010

Evaluation Report for the White Team Drill, July 20, 2010

August 10, 2010

Evaluation Report for the White Team Drill, September 1, 2010

October 20, 2010

Evaluation Report for the White Team Drill, October 27, 2010

November 22, 2010

Evaluation Report for the Red Team Drill, March 2, 2011

September 14, 2011

Evaluation Report for the White Team Drill, June 22, 2011

September 15, 2011

Evaluation Report for the Blue Team Drill, August 10, 2011

September 14, 2011

Evaluation Report for the Blue Team Drill, February 8, 2012

PROCEDURES

NUMBER TITLE REVISION 0ERP01-ZV-EF01 EOF Director

0ERP01-ZV-EF03 Radiological Director

0ERP01-ZV-EF15 Dose Assessment Specialist

0ERP01-ZV-IN01 Emergency Classification

0ERP01-ZV-IN02 Notification to Offsite Agencies

0ERP01-ZV-IN03 Emergency Response Organization Notification

0ERP01-ZV-IN04 Assembly and Accountability

0ERP01-ZV-IN06 Radiological Exposure Guidelines

0ERP01-ZV-IN07 Offsite Protective Action Recommendations

0ERP01-ZV-OS01 OSC Coordinator

0ERP01-ZV-OS06 Emergency Teams

0ERP01-ZV-SH04 Acting OSC Coordinator

NUMBER TITLE REVISION 0ERP01-ZV-TS01 TSC Manager

0ERP01-ZV-TT01 Offsite Dose Calculations

0PGP03-ZX-0002 Condition Reporting Process

0PGP05-ZV-0016 Radiological Coordinator

0PGP05-ZV-0017 Severe Accident Management

Section 4OA1: Performance Indicator Verification

MISCELLANEOUS

NUMBER TITLE REVISION

PI-0002 NRC & INPO Performance Indicator:

Initiating Events Cornerstone (by Unit) and Barrier Integrity Cornerstone (by Unit) Desktop Guidelines

4, 5

South Texas Project Emergency Plan

PROCEDURES

NUMBER TITLE REVISION 0PGP05-ZV-0006 Emergency Notification and Response System

0PGP05-ZV-0007 Prompt Notification System

0PGP05-ZV-0013 Performance Indicator Tracking Guide

0PGP05-ZV-0016 Prompt Notification System Implementing Procedure Updated Prompt Notification System Design Report, Chapter 3 1 Section 4 O A 2:

Problem Identification and Resolution

CONDITION REPORTS

2-2860 12-21347 12-21685 12-23 27 1 12-5448 12-21420 12-22543

PROCEDURES

NUMBER TITLE REVISION 0PGP03-ZX-0002 Condition Reporting Process

2, 43

Section 4 O A 3:

Followup of Events and Notices of Enforcement Discretion

CONDITION REPORTS

11-7747 12-10874

PROCEDURES

NUMBER TITLE REVISION

LDG-06 Preparation of LERs

Section 4OA7:

Licensee

-Identified Violations

CONDITION REPORT

11-7747