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IR 05000293-10-005, on 10/01/2010 - 12/31/2010, Pilgrim Nuclear Power Station, Maintenance Risk Assessments and Emergent Work Control, Identification and Resolution of Problems
	ML110390343
Person / Time
Site:	Pilgrim
Issue date:	02/08/2011
From:	Jackson D E; NRC/RGN-I/DRP/PB5
To:	Rich Smith; Entergy Nuclear Operations
References
	IR-10-005
	Download: ML110390343 (39)
	v • d • e

UNITED STATES N UCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KlNG OF PRUSSlA, PA19406-1415 February 8, 2011 Mr. Robert Smith Site Vice President Entergy Nuclear Operations, lnc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT: PILGRIM NUCLEAR POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000293/201 0005

Dear Mr. Smith:

On December 31 ,2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Pilgrim Nuclear Power Station (PNPS). The enclosed inspection report documents the results, which were discussed on January 5,2011, with you and other members of your staff.The inspection examined activities performed 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.

This report documents three NRC-identified findings of very low safety significance (Green). All of these findings were determined to be violations of NRC requirements.

Additionally, a licensee-identified violation which was determined to be of very low safety significance is listed in this report. However, because of the very low safety significance and because they are entered into your corrective action program, the NRC is treating these findings as non-cited violations (NCU consistent with Section 2.3.2.a of the NRC's Enforcement Policy. lf you contest any NCV, you should provide a response within 30 days of the date of this inspection report, with the baiis for your denial, to the Nuclear Regulatory Commission,.ATTN.:

Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region l;the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Senior Resident lnspector at PNPS. ln addition, if you disigree with the cross-cutting aspect assigned to any finding in this report, you should provide J response within 30 days of the date of this inspection report, with the basis for your disagreemeni, to the RegionalAdministrator, Region l, and the NRC Senior Resident lnspector at ptrlpS. The information you provide will be considered in accordance with lnspection Manual Chapter 0305. ln 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 Doiument Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Wrk Docket No.License No.

Enclosure:

cc: dencl: Projects Branch 5 Division of Reactor Projects 50-293 DPR-35 lnspection Report 05000293/201 0005 d

Attachment:

Supplemental Information Distribution via ListServ

SUMMARY OF FINDINGS

lR 05000293/2010005t 1010112010-1213112010;

Pilgrim Nuclear Power Station; Maintenance Risk Assessments and Emergent Work Control; ldentification and Resolution of Problems.The report covered a three-month period of inspection by the resident and regional-based inspectors.

Three Green NR0-identified non-cited violations (NCV) and one licensee-identified violation of very low safety significance (Green) were identified.

The significance of most findings is indicated by their color (Green, White, Yellow, Red) using lnspection Manual Chapter (lMC)0609, "Significance Determination Process." Cross-cutting aspects associated with findings are determined using IMC 0310, "Components Within the Cross-Cutting Areas." 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: Mitigating

Systems

Green.

The inspectors identified a Green non-cited violation (NCV) of 10 CFR 50.65 paragraph (aX4) for Entergy's failure to correctly assess and manage a Yellow risk condition for planned testing of the High Pressure Coolant Injection (HPCI) system from the Alternate Shutdown Panel (ASP). Specifically, Entergy considered HPCI available by crediting multiple manual actions to restore the automatic function.

However, these actions were not "feW' or "simple" and would not have restored the HPCI automatic function in a timeframe consistent with guidance discussed in NUMARC 93-01, "lndustry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." In addition, HPCI's automatic function would not have been restored in a timeframe consistent with Pilgrim's Updated Final Safety Analysis Report (UFSAR), Section 6.4.1, which specifies 90 seconds for HPCI to reach its required design flow rate. Corrective actions included issuing a standing order to alert Operators of the specific requirements to maintain a system "available" during maintenance and testing. Corrective actions planned include revising Entergy's Risk Assessment Procedure to verify systems credited as"available" have clear and simple direction to restore automatic functional status during maintenance and testing.This finding was determined to be more than minor because Entergy's elevated plant risk would put the plant into a higher risk category and require additional risk management actions, namely protecting the Reactor Core lsolation Cooling system. In addition, the finding affected the Human Performance attribute of the Mitigating System's cornerstone objective to ensure the availability of systems to respond to initiating events and prevent undesirable consequences.

The inspectors performed an evaluation in accordance with IMC 0609, "Significance Determination Process," Appendix K, "Maintenance Risk Assessment and Risk Management Significance Determination Process," because the finding related to Entergy's assessment and management of risk. The finding was determined to be of very low safety significance (Green) because the lncremental Core Damage Probability Deficit for the unavailability of HPCI for the duration of the activity was less than 1.0E-6 per year (approximately 2.6E-9 per year). The inspectors determined that this finding had a cross-cutting aspect in the Human Performance cross-cutting area, Work 4 Control component, because Entergy did not correctly plan and coordinate work activities by incorporating appropriate risk insights H.3(a). (Section 1R13)Green. The inspectors identified an NCV of 10 CFR 50, Appendix B, Criterion X,"lnspection," for the failure to ensure that Quality Control verification inspections were consistently included and correctly specified in quality-affecting procedures and work instructions for construction-like work activities as required by the Quality Assurance Program. Entergy initiated prompt fleet-wide corrective actions to ensure proper work order evaluation and proper inclusion of Quality Control verification inspections.

This issue was entered into the corrective action program as condition reports (CR) CR-HON 2009-01 1 84 and CR-HQN-2010-001 3.The failure to ensure that adequate Quality Control verification inspections were included in quality-affecting procedures and work instructions as required by the Quality Assurance Program was a performance deficiency.

This issue was more than minor because, if left uncorrected, it could lead to a more significant safety concern; in that, the failure to check quality attributes could involve an actual impact to plant equipment.

This issue affected the Design Control attribute of the Mitigating Systems cornerstone because missed or improper quality control inspections during plant modifications could impact the availability, reliability, and capability of systems needed to respond to initiating events. This performance deficiency was determined to be of very low safety significance (Green), since it was confirmed to involve a qualification deficiency that did not result in a loss of operability or functionality.

The inspectors determined that this issue had a cross-cutting aspect in the Human Performance cross-cutting area, Decision-Making component, because the licensee did not have an effective systematic process for obtaining interdisciplinary reviews of proposed work instructions to determine whether Quality Control verification inspections were appropriate

H.1(a). (Section 4OA2)Green. The inspectors identified an NCV of 10 CFR 50, Appendix B, Criterion ll, "Quality Assurance Program," for the failure to implement the experience and qualification requirements of the Quality Assurance Program. As a result, the licensee failed to ensure that an individual assigned to the position of Quality Assurance Manager met the qualification and experience requirements of ANSI/ANS 3.1-1 978 as required by the Quality Assurance Program. Specifically, the individual assigned to be the responsible person for the licensee's overall implementation of the Quality Assurance Program did not have at least one year of nuclear plant experience in the overall implementation of the Quality Assurance Program within the quality assurance organization prior to assuming those responsibilities.

This issue was entered into the corrective action program as CR-HQN-2010-00386.

The failure to ensure that an individual assigned to the position of Quality Assurance Manager met the qualification and experience requirements of ANSI/ANS 3.1-1978 as required by the Quality Assurance Program was a performance deficiency.

This issue was more than minor because, if left uncorrected, it could create a more significant safety concern. The failure to have a fully qualified individual providing overall oversight to the Quality Assurance Program had the potential to affect all cornerstones, but the inspectors determined that this finding will be tracked under the Mitigating Systems cornerstone as the area most likely to be impacted.

The issue was not suitable for quantitative assessment using existing NRC Significance Determination Process (SDP) guidance, so it was determined to be of very low safety significance (Green) using NRC Inspection Manual Chapter (lMC) 0609, Appendix M, "Significance Determination Process Using Qualitative Criteria." The inspectors determined that there was no cross-cutting aspect associated with this finding because this issue was not indicative of current performance as it occurred more than three years ago. (Section 4OA2)Other Findinqs A violation of very low safety significance, which 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. The violation and corrective action tracking numbers are listed in Section 4OA7.Enclosure 6

REPORT DETAILS

Summarv of Plant Status Pilgrim Nuclear Power Station (PNPS) began the inspection period operating at 100 percent power. On October 13,2010, operators reduced power to 50 percent to perform a thermal backwash on the main condenser.

Pilgrim returned to 100 percent power on October 14, 2010.On November 11 ,2010, operators reduced power to 45 percent for a backwash of the main condenser.

Pilgrim returned to 100 percent power later the same day. On November 30, 2010, operators reduced power to 70 percent to perform control rod blade'channel interference testing and returned to 100 percent power later the same day. On December 22,2010, operators reduced power to 50 percent to perform a condenser backwash and returned to 100 percent power on December 23,2010. On December 27,2010, operators reduced power to 50 percent in response to high screen wash differential pressure due to a significant coastal storm. Pilgrim returned to 100 percent power later the same day. Operators maintained the reactor at or near 100 percent power for the remainder of the inspection period.1. REACTORSAFETY Cornerstones:

Initiating Events, Mitigating Systems, and Barrier Integrity 1R04 Eouipment Aliqnment (711 11.04)Partial Svstem Walkdowns (7 1 1 11

.04 O)a. Inspection

Scope (3 samples)The inspectors performed three partial system walkdowns during this inspection period.The inspectors performed a partial walkdown of each system to determine if the critical portions of the selected systems were correctly aligned in accordance with procedures, and to identify any discrepancies that may have had an effect on operability.

The walkdowns included selected control switch position verifications, valve position checks, and verification of electrical power to critical components.

In addition, the inspectors evaluated other elements, such as material condition, housekeeping, and component labeling.

The documents reviewed are in the Attachment.

The following systems were reviewed based on their risk significance for the given plant configuration:. 'B' Emergency Diesel Generator (EDG) with 'A' Residual Heat Removal out of service;. 'A' EDG with 'B' Core Spray and 345KV Line 342 out of service; and o 'B' Reactor Protection System Train while on backup power supply from B-10.b. Findinos No findings were identified.

7 1R05 Fire Protection (71 11 1.05)Fire Protection - Tours (71111.05O)a. lnspection Scope (5 samples)The inspectors performed walkdowns of five fire protection areas during the inspection period. The inspectors reviewed Entergy's fire protection program to determine the fire protection design features, fire area boundaries, and combustible loading requirements for the selected areas. The inspectors walked down these areas to assess Entergy's control of transient combustible material and ignition sources. ln addition, the inspectors evaluated the material condition and operational status of fire detection and suppression capabilities and fire barriers.

The inspectors then compared the existing condition of the areas to the fire protection program requirements to determine whether all program requirements were met. The documents reviewed during this inspection are listed in the Attachment.

The fire protection areas reviewed were:. Fire Area 1.10, Fire Zone 4.1,'B'Emergency Diesel Generator Room;o Fire Area 1.9, Fire Zone 1.9A, 'A' Residual Heat Removal Pipe Room;. Fire Area 1.9, Fire Zone 3.5, Vital Motor Generator Set Room;. Fire Area 1

.10 , Fire Zone 2.1, 'B' Switchgear

and Load Center Room; and. Fire Area 1.10, Fire Zone 2.11A, Turbine Deck-West End.b. Findinss No findings were identified.

1R11 Licensed Operator Requalification

Proqram (71 1 11.1 1)Resident Insoector Quarterlv Review (71111.1 1Q)a. lnspection Scope (1 sample)The inspectors observed licensed operator performance during an annual licensed operator requalification exam involving two evaluated scenarios on October 26,2010.fhe inspectors observed crew response to a Station Blackout scenario complicated by a Loss of Coolant Accident.

ln addition, the inspectors observed a fuel failure scenario with an unisolable leak from the Reactor Water Cleanup system. The inspectors assessed the licensed operators' performance to determine if the training evaluators adequately addressed observed deficiencies.

The inspectors reviewed the applicable training objectives from the scenarios to determine if they had been achieved.

ln addition, the inspectors performed a simulator fidelity review to determine if the arrangement of the simulator instrumentation, controls, and tagging closely paralleled that of the control room.The documents reviewed during this inspection are listed in the Attachment.

I b. Findinos No findings were identified.

1R12 Maintenance

Effectiveness (71 1 1 1

.12 Q)Inspection

Scope (2 samples)The inspectors reviewed the two samples listed below for items such as:

(1) appropriate work practices;

(2) identifying and addressing common cause failures;

(3) scoping in accordance with 10 CFR 50.65 paragraph

(b) of the Maintenance Rule;

(4) characterizing reliability issues for performance;

(5) trending key parameters for condition monitoring; (6)charging unavailability for performance;

(7) classification and reclassification in accordance with 10 CFR 50.65 paragraph (aX1) or (aX2); and

(8) appropriateness of performance criteria for structures, systems, and components (SSCs)/functions classified as paragraph (aX2) and/or appropriateness and adequacy of goals and corrective actions for SSCs/functions classified as paragraph (aX1). The documents reviewed during this inspection are listed in the Attachment.

ltems reviewed included the following:

o Post Accident Sampling System Maintenance Rule (aX1) Action Plan; and o Condition Monitoring of Building and Structures.

b. Findinos No findings were identified.

1 R13 Maintenance Risk Assessments and Emerqent Work Control (71 1 1 1

.13 )a. Inspection

Scope (3 samples)The inspectors evaluated three maintenance risk assessments for planned testing and maintenance activities.

The inspectors reviewed maintenance risk evaluations, work schedules, and control room logs to determine if concurrent maintenance or surveillance activities adversely affected the plant risk already incurred with out-of-service components.

The inspectors evaluated whether Entergy took the necessary steps to control work activities, minimized the probability of initiating events, and maintained the functional capability of mitigating systems. The inspectors assessed Entergy's risk management actions during plant walkdowns.

The documents reviewed during this inspection are listed in the Attachment.

The inspectors reviewed the conduct and adequacy of maintenance risk assessments for the following maintenance and testing activities:. Green Risk for Testing and Maintenance on the 'B' Core Spray System, Line 342, the Diesel Fire Pump, and the DieselAir Compressor;. Yellow Risk for'B' Residual Heat Removal Maintenance; and. Green Risk for High Pressure Coolant lnjection System Testing from the Alternate Shutdown Panel.Enclosure b.9 Findinos lntroduction:

The inspectors identified a Green NCV of 10 CFR 50.65 paragraph (a)( ) for Entergy's failure to correctly assess and manage a Yellow risk condition during testing of the HPCI system from the Alternate Shutdown Panel (ASP). Specifically, Entergy considered HPCI available by crediting multiple manual actions to restore the automatic function.

However, these actions were not "few" or "simple" and would not have restored the HPCI automatic function in a timeframe consistent with guidance discussed in NUMARC 93-01, "lndustry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," nor with Pilgrim's UFSAR.Description:

On November 15,2010, Entergy performed surveillance testing of HPCI from the ASP. During this test, operators place a control switch on the ASP from "remote" to"local" which removes the automatic function of HPCI to mitigate a Loss of Coolant Accident.

Entergy's Equipment Out of Service (EOOS) risk assessment model calculates the risk with HPCI out of service to be "Yellow." However, Entergy credited a local operator and manual actions to restore the HPCI automatic function during the test and thereby considered HPCI available and managed the plant risk as "Green." NUMARC 93-01, Section 11, Appendix B, Revision 2, dated 212212000, discusses manual restoration actions to maintain a system available during the conduct of testing which removes the automatic function.

NUMARC 93-01, discusses that, "Restoration actions must be contained in a written procedure, must be uncomplicated (a single action or a few simple actions), and must not require diagnosis or repair." ln order to restore HPCI, Operations briefed restoration steps in procedure 8.5.4.6, "HPCI Pump and Valve Operability from Alternate Shutdown Panel." The briefing sheet included, in part,"performing Section 8.2, starting at step-6, and then section 8.4for system restoration." Approximately 25 steps were required to be performed to restore HPCI's automatic function, Entergy did not recognize that the number of steps required to restore HPCI's automatic function would not meet a timeframe consistent with the guidelines in NUMARC 93-01 to assure the automatic function was maintained.

In addition, HPCI's automatic function would not have been restored in a timeframe consistent with Pilgrim's UFSAR Section 6.4.1, which specifies a 90 second timeframe for HPCI to reach its required design flow rate. As a result, Entergy did not recognize that risk should have been Yellow and that risk management actions, including protecting the Reactor Core lsolation Cooling System (RCIC) system, would be required.Analysis:

The performance deficiency associated with this finding is that Entergy performed an incorrect risk assessment for HPCI testing from the ASP and, as a result, did not take all necessary risk management actions as specified by 10 CFR 50.65 paragraph (aX4). Traditional Enforcement did not apply as the issue did not have actual or potential safety consequence, had no willful aspects, nor did it impact the NRC's ability to perform its regulatory function.A review of NRC Inspection Manual Chapter (lMC) 0612, Appendix E, "Minor Examples," identified that Section 7, "Maintenance Rule," Example'e', reflected a similar more than minor example. Specifically, this finding was determined to be more than minor because Entergy's elevated plant risk would put the plant into a higher risk category and require Enclosure 10 additional risk management actions, namely protecting the RCIC system. In addition, the finding affected the Human Performance attribute of the Mitigating System's cornerstone objective to ensure the availability of systems to respond to initiating events and prevent undesirable consequences.

The inspectors performed an evaluation in accordance with IMC 0609, "Significance Determination Process," Appendix K, "Maintenance Risk Assessment and Risk Management Significance Determination Process," because the finding related to Entergy's assessment and management of risk. The finding was determined to be of very low safety significance (Green) because the Incremental Core Damage Probability Deficit for the unavailability of HPCI for the duration of the activity was less than 1.0 E-6 per year (approximately 2.6 E-9 per year).The inspectors determined that this finding had a cross-cutting aspect in the Human Performance cross-cutting area, Work Control component, because Entergy did not plan and coordinate work activities by incorporating appropriate risk insights.

H.3(a)]Enforcement:

10 CFR 50.65 paragraph (aX4), "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," states, in part, "...the licensee shall manage the increase in risk that may result from the proposed maintenance activities." Contrary to the above, on November 15, 2010, Energy incorrectly managed the increase in risk from testing HPCI from the ASP. As a result, Entergy did not recognize a Yellow risk condition and thus did not take all appropriate risk management actions.Corrective actions included issuing a standing order to alert Operators of the specific requirements to maintain a system "available" during maintenance and testing. Corrective actions planned include revising Entergy's Risk Assessment Procedure to verify systems credited as "available" have clear and simple direction to restore automatic functional status during maintenance and testing. Because of the very low safety significance and because it has been entered into the corrective action program (CR-PNP-2010-4267), the NRC is treating this as an NCV, consistent with Section 2.3.2 a of the NRC's Enforcement Policy. (NCV 05000293/2010005-01, Failure to Manage a Yellow Risk Condition During HPGlTesting from the Alternate Shutdown Panel.)1R15 Operabilitv Evaluations (71111.15)

a. Inspection Scope

(5 samples)The inspectors reviewed five operability determinations associated with degraded or non-conforming conditions to determine if the operability determination was justified and if the mitigating systems or barriers remained available such that no unrecognized increase in risk had occurred.

The inspectors also reviewed compensatory measures to determine if the compensatory measures were in place and were appropriately controlled.

The inspectors reviewed Entergy's performance against related Technical Specifications and UFSAR requirements.

The documents reviewed during this inspection are listed in the Attachment.

The inspectors reviewed the following degraded or non-conforming conditions;. Transfer Switch Y-10 acting sluggishly when transferring back to normal power supply;. 'A' Emergency Diesel Generator jacket water temperature switch found defective; o Degradation of Main Breakwater Structure; 11. Residual Heat Removal/ Fuel Pool Cooling supports degraded; and o Drain Valve on the 'D' Moisture Separator Drain Tank not maintaining normal level.b. Findinqs No findings were identified.

1 R19 Post-Maintenance Testinq (71 1 1 1

.19 )a. Inspection

Scope (5 samples)The inspectors reviewed five samples of post-maintenance tests during this inspection period. The inspectors reviewed these activities to determine whether the post maintenance test adequately demonstrated that the safety-related function of the equipment was satisfied given the scope of the work performed, and that operability of the system was restored.

In addition, the inspectors evaluated the applicable test acceptance criteria to verify consistency with the associated design and licensing bases, as well as Technical Specification requirements.

The inspectors also evaluated whether conditions adverse to quality were entered into the corrective action program for resolution.

The documents reviewed during this inspection are listed in the Attachment.

The following maintenance activities and their post-maintenance tests were evaluated:. Reactor Core lsolation Cooling maintenance for valves MO-1301-26, MO-1301-22, and MO-1301-25;. Line 342 Maintenance;. Troubleshooting

'B' Reactor Protection System Spurious Half-Scrams;. 'A' Emergency Diesel Generator Start Push Button Replacement and Other Preventative Maintenance; and o Replace Main Stack Dilution Fan'B'(VSF-2068).

b. Findinos No findings were identified.

1R22 Surveillance

Testino (7 11 1 1.22)lnspection Scope (5 samples)The inspectors witnessed five surveillance activities andlor reviewed test data to determine whether the testing adequately demonstrated equipment operational readiness and the ability to perform the intended safety-related functions.

The inspectors reviewed selected prerequisites and precautions to determine if they were met, and if the tests were performed in accordance with the procedural steps. Additionatly, the inspectors evaluated the applicable test acceptance criteria for consistency with associated design bases, licensing bases, and Technical Specification requirements.

The inspectors also evaluated whether conditions adverse to quality were entered into the corrective action program for Enclosure 12 resolution.

The documents reviewed during this inspection are listed in the Attachment.

The following surveillance tests were evaluated:. 'A' Emergency Diesel Generator Operability;. 'B'and 'D' Residual Heat Removal Pump Operability (lST);. High Pressure Coolant Injection (HPCI) Quarterly Operability Test (lST);o Control Blade Interference Testing; and. 'B' Core Spray Pump Operability and Flow Rate Test (lST).b. Findinqs No findings were identified.

2. RADTATTON

SAFETY (RS)Cornerstone:

Occupational/Public Radiation Safety 2RS01 Radioloqical Hazard Assessment and Exposure Controls (71124.01)

a. Inspection Scope

(1 Sample)During the period October 18 through October 21, 2010, the inspectors conducted the following activities to verify that Pilgrim properly assessed the radiological hazards in the workplace and implemented appropriate radiation monitoring and exposure controls during routine operations.

lmplementation of these controls was reviewed against the criteria contained in 10 CFR 20, "Standards for Protection Against Radiation," relevant Technical Specifications, and the licensee's procedures.

This inspection activity represents the completion of one sample relative to this inspection area; completing the annual inspection requirement.

Radiolooical Hazard Assessment. The inspectors verified air samples were collected and analyzed in accordance with Pilgrim procedures.

Instructions to Workers. The inspectors ver:ified that workers would be informed of changing conditions by the radiological controls technician providing continuous job coverage.Contamination and Radioactive Material Control. The inspectors observed the Radiological Control Area exit at the "green line" to verify the surveying and release of material was in accordance with plant procedures.

The inspectors verified the procedures are sufficient to control the spread of contamination and prevent unintended release of licensed materialfrom the site.Enclosure 13. The inspectors verified that Pilgrim has not established a de facto "release limit" by altering the instrument's typical sensitivity through altering energy discrimination or placing instruments in high background radiation areas.Radioloqical Hazards Control and Work Coveraqe o There were no opportunities to observe work in areas with significant dose gradients during this inspection period.o Pilgrim has no posted airborne radiation areas. Therefore, the inspectors had no opportunities to observe work in such areas and could not evaluate controls for those areas.. The inspectors verified the physical and programmatic controls for highly activated materials stored in the spent fuel pool to ensure that appropriate controls are in place to preclude the inadvertent removal of these materials from the pool.. The inspectors verified the posting and physical controls for the Traversing In-Core Probe (TlP) room were appropriate when TIP movement was in progress.

This area was a very high radiation area (VHRA) at the time of the observation.

Risk-Siqnificant Hiqh Radiation Area and Verv Hioh Radiation Area Controls o The inspectors discussed the VHRA controls and procedures with the Radiation Protection Manager (RPM).. The inspectors discussed the controls in place for entry into the TIP room with a Radiation Protection (RP) supervisor.

The inspector verified that communication with the RP group is required prior to moving probes. The RP supervisor is on a tag out that must be cleared prior to probe movement.. The inspectors verified that an individual is not able to gain unauthorized access to the TIP room during probe movement.b. Findinos No findings were identified.

2RS02 Occupational ALARA Planninq and Controls (71124.02)a. lnspection Scope (4 samples)During the period October 18 through October 21, 2010, the inspectors performed the following activities to verify that the licensee was properly implementing operational, engineering, and administrative controls to maintain personnel exposure As Low As Reasonably Achievable (ALARA) for activities performed during routine operations.

lmplementation of these controls was reviewed against the criteria contained in 10 CFR 20, applicable industry standards, and the licensee's procedure.

b.4.14 Inspection Plannino. The inspectors reviewed pertinent information regarding cumulative exposure history, current exposure trends, and ongoing activities.

The inspectors reviewed the site's 3-year rolling average dose and compared the site's average with the industry's average.. The inspectors reviewed Pilgrim's trend in collective exposure and the site's source term measurements.

Verification of Dose Estimates and Exposure Trackino Svstems r The inspectors verified that Pilgrim has established measures to track, trend, and set trigger points to prompt additionalALARA planning and controls.. The inspectors performed an evaluation of Pilgrim's method of adjusting exposure estimates when unexpected changes occur.Findinos No findings were identified.

orHER ACTTVTTTES

[OA]4OA1 Performance lndicator Verification (71 151).1 Cornerstone:

Mitigating Systems

a. Inspection Scope

(2 samples)The inspectors reviewed Performance lndicator (Pl) data to determine the accuracy and completeness of the reported data. The review was accomplished by comparing reported Pl data to confirmatory plant records and data available in plant logs, Condition Reports (CRs), Licensee Event Reports (LERs), and NRC inspection reports. The acceptance criteria used for the review was Nuclear Energy lnstitute (NEl) 99-02, Revision 6,"Regulatory Assessment Performance Indicator Guidelines." The documents reviewed during the inspection are listed in the Attachment.

The following performance indicators were reviewed: o Emergency AC Power System from the fourth quarter 2009, through the third quarter of 2010 [MS06]; and. Cooling Water (Salt Service Water/Reactor Building Closed Cooling Water) from the fourth quarter 2009 through the third quarter of 2010 [MS10].b. Findinqs No findings were identified.

.2 15 Cornerstone:

Occupational/Public Radiation Safety Occupational Exposure Control Effectiveness Inspection Scope (1 sample)The inspectors reviewed implementation of the licensee's Occupational Exposure Control Effectiveness Performance Indicator (Pl) Program. Specifically, the inspector reviewed recent condition reports and associated documents for occurrences involving locked high radiation areas, very high radiation areas, and unplanned exposures against the criteria specified in Nuclear Energy Institute (NEl) 99-02, "Regulatory Assessment Performance lndicator Guideline," to verify that all occurrences that met the NEI criteria were identified and reported as performance indicators.

This inspection activity represents the completion of one sample relative to this inspection area; completing the annual inspection requirement.

Findinqs No findings were identified.

ldentification and Resolution of Problems (71 '152)Review of ltems Entered into the Corrective Action Prooram (CAP)Inspection Scope The inspectors performed a screening of each item entered into Entergy's corrective action program. This review was accomplished by reviewing printouts of each CR, attending daily screening meetings and/or accessing Entergy's database.

The purpose of this review was to identify conditions such as repetitive equipment failures or human performance issues that might warrant additional follow-up.

Findinqs No findings were identified.

Semi-Annual Review to ldentifv Trends Insoection Scope (1 sample)The inspectors performed a review of Entergy's CAP and associated documents to identify trends that could indicate the existence of a more significant safety issue. The review was focused on repetitive equipment and corrective maintenance issues, but also considered the results of daily inspector CAP item screening.

The review included issues documented in CAP trend reports and the site CAP performance indicator data. The review focused on the six month period of July 2010, through December 2010, although the inspectors also evaluated previous trend results for CRs and observations from selected inspection samples from January 2010 through June 2010 which have been Enclosure b.4c.42 ,1 a.b..2 a.

b.16 discussed previously in Pilgrim lntegrated Inspection Report 2010003 (M1102100150).

The documents reviewed during the inspection are listed in the Attachment.

Findinqs and Observations No findings were identified.

One low level trend discussed in Pilgrim Integrated Inspection Report 2010003 was reviewed and is discussed below.Maintenance Rule Prooram The inspectors reviewed CR-PNP-2009-4197 and CR-PNP-2010-2211, which were written to perform assessments of the Maintenance Rule Program (MRP) and the Maintenance Rule Functional Failure evaluation process. The inspectors performed additional Maintenance Rule inspection samples during the 3'd and 4th quarters of 2010, and identified fewer deficiencies in the MRP, the scoping of systems into the MRP, and in functionalfailure evaluation quality. In addition, the inspectors noted improved Maintenance Rule Committee oversight and discipline and ownership by engineers for their MRP products.

Due to the identification of fewer deficiencies and because corrective actions to improve the MRP and Maintenance Rule Functional Failure evaluation quality at Pilgrim appear to have been effective, the inspectors consider this low level trend closed.Selected lssue Follow-up Inspection Inspection Scope An inspection was performed at the Entergy corporate office in Jackson, Mississippi on June 14 through 17 , 2010, to review the circumstances surrounding missed quality control (QC) verification inspections documented in CR-HQN-2009-01184 and CR HQN 2010 00013. The issue involved QC verification inspections performed during construction-related activities which were required as part of the Entergy quality oversight and verification programs.

The inspection was performed to determine if the licensee had taken corrective actions commensurate with the significance of the identified issues, and to assess the impact, if any, on the operability of plant equipment caused by the missed inspections.

This inspection was conducted by inspectors from Regions l, ll, and lV, as well as a Senior Program Engineer from the Quality and Vendor Branch of the Office of Nuclear Reactor Regulation (NRR). The inspection covered all NRO-licensed sites owned by Entergy Operations, lnc., including Arkansas Nuclear One, James A. Fitzpatrick, Grand Gulf Nuclear Station, lndian Point Units 2 and 3, Palisades Plant, Pilgrim Nuclear Power Station, River Bend Station, Vermont Yankee, and Waterford 3.The inspectors reviewed root cause analyses documented in CR-HQN-2009-01184 and CR-HQN-2010-00013, and the results of the licensee's extent of condition reviews and plant impact assessments.

The inspectors also independently assessed the potential impacts of the missed inspections on the operability of plant equipment by reviewing all of the examples identified by the licensee, and by independently reviewing completed modifications and work orders to identify additional examples.

The inspectors also reviewed the corrective action database to assess reported equipment failures in order to assess whether the failure might have involved missed QC verification inspections.

.3 a.

I 17 The inspectors assessed causal factors that may have contributed to missing QC verification inspections.

This assessment included reviewing the Entergy Quality Assurance Program Manual (OAPM) requirements, changes made to the QAPM, and the level of agreement between the QAPM and its implementing procedures.

Documents reviewed are listed in the attachment.

b. Findinqs Backqround:

The inspectors identified problems with the implementation of elements of the Quality Assurance (QA) Program that affected the fleet of Entergy Operations Inc., (hereafter referred to as "Entergy")

nuclear power plants that are licensed by the NRC.While the plant organizations are NRC licensees, Entergy also has corporate groups which are not NRC licensees that are actively involved in some activities affecting sites, including program and procedure changes. Entergy adopted a business strategy of adopting standard programs and procedures at all fleet plants.On October 30, 2009, the NRC discussed with Entergy the initial concerns about whether QC verification inspections were being performed consistently for the types of work that require that level of inspection.

Both the non-licensed and licensed Entergy organizations responded with an appropriate review of the issues. Entergy's review of work documents that were potentially affected was extensive at each site. Entergy's total review examined over 320 Engineering Change documents and 2676 Work Orders. Of the 30 Work Orders identified to have QC verification inspection deficiencies affecting eight safety-related design changes, all 30 were determined by Entergy to have sufficient documentation to provide confidence that the equipment was installed correctly.

Specific corrective actions were identified and implemented to ensure that QC verification inspections would be included in current and future work documents, including procedure enhancements.

The information provided to the NRC was used to perform a focused inspection in order to assess the impact of the missed verification inspections at each of the NRC-licensed facilities.

The inspection documented below independently assessed the potential impact of missed QC verification inspections on the operability of plant equipment, as well as assessing details of QA Program for the Entergy fleet.Two findings were identified during this inspection.

These findings involved missed QC verification inspections at seven Entergy sites, and the assignment of individuals to the QA Manager position that did not meet the experience and qualification requirements at eight sites. Only the findings impacting Pilgrim are described below.The inspectors concluded that the Entergy fleet organizational structure and Entergy strategy of adopting standardized procedures across the fleet were contributing factors to thefindings.

Specifically:

o Changes to adopt the standard fleet QA program created a partial conflict with existing requirements for worker qualifications at some sites. The process for creating and revising standardized fleet procedures and programs used to meet NRC requirements b.1 18 must ensure that site-specific regulatory requirements and commitments are properly addressed for all sites.. Changes that removed details from existing site-specific QA and QC program implementing procedures while shifting to standardized fleet procedures contributed to the finding involving missed QC verification inspections.

CRs at individual sites regarding problems related to this issue were not recognized collectively as symptoms of a problem with these procedures because they were addressed at the site level.Failure to Perform Required Qualitv Control Inspections

Introduction:

The inspectors identified a Green, NCV of 10 CFR 50, Appendix B, Criterion X, "lnspection," for the failure to ensure that Quality Control verification inspections were included in quality-affecting procedures and work instructions for construction-like work activities as required by the Quality Assurance Program.Description:

ln response to the inspectors' request for information concerning implementation of the quality oversight and verification programs, the licensee performed a review of a representative sample of engineering changes and work order tasks issued between 2006 and 2009. The licensee's review included performing equipment walkdowns, evaluating rework rates and human error rates, and causes for failures of significant components.

Based on the results of these reviews, Entergy initiated CRs at the various sites to document problems with Quality Control (QC) verification activities and failures to perform required QC reviews of safety-related engineering changes and construction related work activities.

Entergy's investigation concluded that procedures contained inadequate guidance, which resulted in inconsistent implementation of the QC Program. Specifically, some safety-related design change work orders were not reviewed to determine whether QC verification inspections were required, and some safety-related design change work orders did not include all required QC verification inspections.

These examples were documented in CR-HQN-2009-01083, -01084, -01085, -01093, -01096, -01 140, -01 169, -01170, -01184, and -01 188.Additional findings identified by Entergy's review included: o Managers in maintenance organizations did not have a detailed understanding of QC responsibilities, required inspections, or what documents required review (CR HQN-2009-01 150).. A weakness was identified in the process for ensuring proper approval of contract QC inspection personnel at all Entergy sites. Procedure EN-QV-1 11, "Training and Certification of Inspection/verification and examination Personnel," Section 4.0 [1], required that the Manager responsible for Quality Assurance or designee at each location is responsible for approving ANSI N45.2.6 certification of QC inspection personnel.

In practice, contract QC inspectors'qualifications were not approved by the QA Manager prior to November of 2009. This was determined to be a minor violation because the ANSI Level lll inspector at each site was documenting that the contract QC personnel had the necessary qualifications to perform the inspections for which Enclosure 19 they were contracted.

This issue was entered into the licensee's corrective action program as CR-HQN-2009-1 091 .o At individual Entergy plants, 27 condition reports were written in 2008 and 2009 to document potentially missed QC verification inspections or missed reviews to consider QC verification inspections prior to the NRC engaging Entergy on this issue. Of those, seven were actual missed inspections (CR-RBS-2009-05041, CR-JAF-2008-03648, and CR-PNP-2008-0091 6 and CR-PNP-2008-03922, CR-PNP-2009-01 798, CR-PNP-2009-02059, and CR-PNP-2009-02255).

Multiple condition reports documented work package quality issues that impacted the ability to identify appropriate QC verification inspection req uirements.

o Two examples of QC programmatic issues were identified, assigned by Entergy headquarters, and not properly addressed (CR-ANO-C-2009-01884, and CR-HQN-2009-00178).

These were considered examples of the violation discussed below.o River Bend Station was using notification points instead of designating specific QC hold points (CR-RBS-2008-04685).

o Insufficient resources were assigned or qualified to perform the required tasks at Grand Gulf Nuclear Station and River Bend Station. River Bend Station operated with a single QC Level ll inspector for more than 3 years, and Grand Gulf Nuclear Station's two QC inspectors did not have all of the discipline certifications for which they were conducting inspections (CR-HON-2009-01 140 and CR GGN-2009-06575).

While these conditions were inappropriate, the inspectors did not identify a separate violation associated with these issues. To the extent that the individuals at River Bend Station were evaluating work documents for QC verification inspections and not correctly identifying those verifications, those examples are part of the violation discussed below.e Although equipment-related QC condition reports were addressed appropriately, QC programmatic issues were not always effectively addressed.. QA audits and oversight activities for the QC Program missed opportunities to identify the findings of their investigation (CR-HQN-2009-01169, CR-HQN-2009-0153, and CR-HQN-2O10-00013).

In particular, the Entergy corporate ANSI Level lll inspector was required to perform periodic surveillances of QC inspection activities to ensure the program is being adequately implemented and maintained, but these required surveillances were not performed in 2008 (CR-HQN-2009-001 11). This is further discussed in Section 4OA7.Subsequent to the identification of these deficiencies, Entergy initiated prompt corrective actions to ensure that appropriate safety-related, engineering changes and non-routine maintenance work orders were identified and routed to the Maintenance lnspection Coordinator for evaluation and inclusion of QC verification inspections in accordance with the revised requirements of procedure EN-WM-105, "Planning." These corrective actions Enclosure 2A and actions to preclude recurrence were collectively documented in the following Level A condition reports: CR-HQN 2009-01 184, dated December 21, 2009, and CR-HQN-2010-0013, dated January 6, 2010.In-office NRC reviews identified the need to conduct further inspection activities.

On June 14 through 17,2010, the inspectors conducted a focused review of work performed at each NRC-licensed Entergy site to assess whether examples of missed QC verification inspections identified by Entergy during their review had the potential to have impacted the operability of important plant equipment.

The inspectors also reviewed the corrective action database and maintenance records to independently assess the rigor of the Entergy review and to identify additional examples of missed QC verification inspections.

The inspectors identified no additional examples, and concluded that the Entergy reviews were sufficient to identify the scope of the problems and develop actions to address the causes.The inspectors reviewed specific work items whose scope met QAPM requirements to have had QC verification inspections but did not have the appropriate inspections.

Based in part on interviews with Entergy personnel, the inspectors determined that procedural guidance for work planning was not sufficiently detailed or clear to ensure that work packages with construction-like activities would be reviewed by the specified QC personnel.

These individuals were responsible for designating the QC inspections that were required by the QAPM.The inspectors also identified.

numerous CRs written at Entergy sites that documented improper implementation of QC verification inspections.

Specific CRs are listed in the attachment.

Analvsis:

The failure to ensure that adequate Quality Control verification inspections were included in quality-affecting procedures and work instructions as required by the Quality Assurance Program was a performance deficiency.

This programmatic deficiency, if left uncorrected, could lead to a more significant safety concern; in that, the failure to check quality attributes could involve an actual impact to plant equipment.

This issue affected the Design Control attribute of the Mitigating Systems cornerstone because missed quality control inspections during plant modifications could impact the availability, reliability, and capability of systems needed to respond to initiating events. This performance deficiency was determined to have very low safety significance since it was confirmed to involve a qualification deficiency that did not result in a loss of operability or functionality.

Specifically, inspectors verified by sampling that work documents provided objective quality evidence that work activities that had missed quality control verifications were properly performed.

The inspectors determined that this issue had a cross-cutting aspect in the Human Performance cross-cutting area, Decision-Making component, because the licensee did not have an effective systematic process for obtaining interdisciplinary reviews of proposed work instructions to determine whether Quality Control verification inspections were appropriate

[H. 1 (a)].Enforcement:

10 CFR Part 50, Appendix B, Criterion X, "lnspection," requires, in part, that, "Examinations, measurements, or tests of material...

shall be performed for each Enclosure 21 work operation where necessary to assure quality . lf mandatory inspection hold points, which require witnessing or inspecting by the licensee's designated representative and beyond which work shall not proceed without the consent of the designated representative are required, the specific hold points shall be indicated in appropriate documents." Entergy's QAPM, Revision 20, Section B.12, "lnspection," requires, in part, that,"Provisions to ensure inspection planning is properly accomplished are to be established.

Planning activities are to identify the characteristics and activities to be inspected, the inspection techniques, the acceptance criteria, and the organization responsible for performing the inspection.

Provisions to identify inspection hold points, beyond which work is not to proceed without consent of the inspection organizatior;

?f* to be defined." Contrary to the above, from February 2006, to December 2009, the licensee failed to ensure that examinations, measurements, or tests of material were performed for each work operation where necessary to assure quality, and failed to include mandatory inspection hold points in appropriate documents.

Specifically, multiple examples of Maintenance Work Orders and Engineering Change documents for construction-related activities involving safety-related systems structures and components were identified where witnessing or inspections were required to be performed to ensure quality, but these steps were not identified, included in the work documents, or performed as required QC hold points in the work instructions.

Condition reports documenting the specific problems and examples of the violation included: cR-PNP-2009-05359; cR-HQN-2009-01083; cR-HQN-2009-01084; cR-HQN-2009-01085; cR-HQN-2009-01093; cR-HQN-2009-01096; CR-HQN-2009-01 140;cR-HQN-2009-01169; OR-HQN-2009-01170; CR-HQN-2009-01 1 84; and cR-HQN-2009-01 188.Because this issue was of very low safety significance and was entered into the CAP as CR-HQN 2009-01184 and CR-HQN-2010-0013, this violation is being treated as an NCV, consistent with Section 2.3.2.a of the NRC's Enforcement Policy (NCV 05000293/2010005-02, Failure to Perform Required Quality Gontrol Inspections).

b.2. Failure to lmplement the Experience and Qualification Reouirements Associated With the Qualitv Assurance Prooram lntroduction:

The inspectors identified a Green NCV violation of 10 CFR 50, Appendix B, Criterion ll, "Quality Assurance Program," for the failure to implement the experience and qualification requirements of the Quality Assurance Program. As a result, the licensee failed to ensure that an individual assigned to the position of Quality Assurance Manager Enclosure 22 met the qualification and experience requirements of ANSI/ANS 3.1-1978 as required by the Quality Assurance Program.Description:

During their review of the issues surrounding the improper implementation of quality control (QC) verifications discussed above, the inspectors noted that the root cause analysis documented in CR-HQN-2O10-0013 identified that lack of experience of the Quality Assurance (QA) Manager contributed to the failure to identify the trend in missed QC verification inspections.

The inspectors reviewed the relevant experience and qualifications of the QA Manager at each Entergy site. The inspectors also reviewed the NRC's safety evaluation report that approved Entergy's original corporate Quality Assurance Program Manual (QAPM), which is the document that contains the QA Program. Additionally, the inspectors reviewed the administrative section of the Technical Specifications for all the Entergy sites and a sample of evaluations, performed in accordance with 10 CFR 50.54(a), that supported Entergy QAPM changes and alignment of plants that were subsequently purchased by Entergy.The Entergy corporate QAPM required each site to meet the experience and qualification standards in ANSI/ANS 3.1-1978, "American National Standard for Selection and Training of Nuclear Power Plant Personnel." Section 4.4 included qualification and experience requirements for the personnel described as "group leaders" of five professionaltechnical groups, including Quality Assurance.

Section 4.4.5, "Quality Assurance," required that"...the responsible person shall have six years experience in the field of quality assurance, preferably at an operating nuclear plant, or operations supervisory experience.

At least one year of this six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance organization)." On December 15, 2008, procedure EN-QV-117, "Oversight Training Program," the Entergy procedure used by all Entergy sites to implement the requirements of ANSI/ANS 3.1-1978, was revised by the Entergy corporate QA group. Section 5.7, "Manager/QA Senior Auditor Training," was changed to state: Either the QA Manager or the Senior QA Auditor will meet the requirements of ANS 3.1-1978 paragraph 4.4.5 for operating plants and it applicable ANS 3.1-1993 paragraph 4.3.7 for new plants.The inspectors reviewed completed Personnel Change Planning ChecklisUForms for QA Managers at each site. Entergy used this form to evaluate QA Manager candidates prior to the implementation of an Entergy fleet-wide restructuring in July 2007. Attachment 8,"Change Management Guidelines for Alignment lmplementation," included the following conclusion for the individual that subsequently was assigned to be the QA Manager: flndividual's name redactedl meets the minimum requirements for QA Manager with the exception of at least one year of this six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. This requirement must be met by the QA Senior Auditor.Enclosure 23 Based on discussions with Entergy corporate QA personnel, the inspectors determined that Entergy personnel had interpreted ANSI/ANS 3.1-1978, Sections 4.4 and 4.4.5 to allow the Senior Auditor to be considered the QA group leader described in the standard for purposes of meeting the experience requirements of Section 4.4.5 in cases where a candidate for the position of QA Manager did not satisfy the experience requirements.

In reviewing this issue, the NRC staff has determined that the group leader in this case is the individual filling the position assigned responsibility for overall implementation of the QA Program (Entergy used the title "QA Manage/'for this position).

The individual meeting the experience and qualification requirements must be the individual assigned the responsibilities for overall implementation of the QA Program assigned within the QA Program.The inspectors determined that this change to procedure EN-QV-117 did not ensure that the qualifications for the QA Manager would meet the requirements of standard.

The inspectors identified an example where the Senior Auditor was credited as being the group leader for purposes of meeting ANSI/ANS 3.1-1978, and the individual who was assigned as the QA Manager did not meet the ANSI/ANS 3.1-1978 experience requirements.

The team also determined that the responsibilities assigned to the QA Manager under the QAPM were not reassigned to the Senior Auditor, and the Senior Auditor did not report directly to the designated senior executive.

The Senior Auditor continued to report to the QA Manager, so the person with the greater experience did not have the positional authority to decide issues.Analvsis:

The failure to ensure that an individual assigned to the position of Quality Assurance Manager met the qualification and experience requirements of ANSI/ANS 3.1-1978 as required by the Quality Assurance Program was a performance deficiency.

This performance deficiency was determined to be more than minor because, if left uncorrected, it could create a more significant safety concern. Failure to have a fully qualified individual providing overall oversight to the QA Program had the potential to affect all cornerstones, but this finding will be tracked under the Mitigating Systems cornerstone as the area most likely to be impacted.

The issue was not suitable for quantitative significance determination, so it was assessed using IMC 0609, Appendix M, and was evaluated using the qualitative criteria listed in Table 4.1. This finding was determined to be of very low safety significance because other quality assurance program functions remained unaffected by this performance deficiency, so defense-in-depth continued to exist. The inspectors determined that there was no cross-cutting aspect associated with this finding because this issue was not indicative of current performance as it occurred more than three years ago.Enforcement:

Appendix B to 10 CFR 50, Criterion ll, "Quality Assurance Program," requires, in part, that the licensee establish a quality assurance program which complies with Appendix B. This program shall be documented by written policies, procedures, or instructions and shall be carried out throughout plant life in accordance with those policies, procedures, or instructions.

The program shall provide for indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintained.

24 The Entergy Quality Assurance Program Manual, Revision 13, is the document used at each Entergy-owned site to describe the quality assurance program. Table 1, Section A of the Quality Assurance Program Manual states, in part, that qualifications and experience for station personnel shall meet ANSI/ANS 3.1-1978 except for positions where an exception to either ANSI/ANS 3.1-1978 or N18.1-1971 is stated in the applicable unit's Technical Specifications.

ANSI/ANS 3.1-1978, Section 4.4.5, "Quality Assurance," states, in part, that the responsible person (i.e. the Quality Assurance Manager) shall have six years experience in the field of quality assurance.

At least one year of this six years experience shall be obtained within the quality assurance organization.

Contrary to the above, between February 22 and June 30, 2010, the licensee failed to implement the quality assurance program requirements intended to provide indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency was achieved and maintained.

Specifically, the individual assigned to be the responsible person for the licensee's overall implementation of the Quality Assurance Program did not have at least one year of nuclear plant experience in the overall implementation of the Quality Assurance Program within the quality assurance organization prior to assuming those responsibilities.

Because this issue was of very low safety significance and was entered into the CAP as CR-HQN-2O10-00386, this violation is being treated as an NCV consistent with Section 2.3.2.a of the NRC's Enforcement Policy.(NCV 05000293/2010005-03, Failure to lmplement the Experience and Qualification Requirements of the Quality Assurance Program).4OA5 Othef Activities Institute of Nuclear Power Operations (INPO) and World Association of Nuclear Operators (WANO) Plant Assessment Report Review

a. Inspection Scope

The inspectors reviewed the report for the INPOMANO plant assessment of the Pilgrim Nuclear Power Station conducted in December 2010. The inspectors reviewed the report to ensure that issues identified were consistent with the NRC perspectives of licensee performance and to verify if any significant safety issues were identified that required further NRC follow-up.

b. Findinqs No findings were identified.

4OAO Meetinqs.

Includinq Exit On October 21,2010, a Radiation Safety exit meeting was conducted with Mr. Stephen Bethay and other members of the Pilgrim staff. The inspectors confirmed that no proprietary information was provided during the inspection.

On January 5,2011, the resident inspectors conducted an exit meeting and presented the preliminary inspection results to Mr. Robert Smith, and other members of the Pilgrim staff.The inspectors confirmed that proprietary information provided or examined during the inspection was controlled andior returned to Entergy, and the content of this report includes no proprietary information.

On January 10,2011, the inspector presented the results of the Selected lssue Follow-up lnspection of quality assurance and quality control issues to Mr. T. White, Manager, Quality Assurance, and other members of the Pilgrim staff. The inspectors confirmed that no proprietary information was provided during the inspection.

40 A7 Licensee-ldentified 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 Section Vl of the NRC Enforcement Policy, NUREG-1600, for being dispositioned as an NCV.Procedure, EN-QV-111, "Training and Certification of lnspectionA/erification and Examination Personnel," Section 4.0 [4](i), requires that the Entergy corporate ANSI Level lll inspector shall perform periodic (annual) surveillances of quality control inspection activities to ensure that the program is being adequately implemented and maintained.

Contrary to the above, no surveillances of quality control inspection activities were performed for any Entergy site during calendar year 2008. The issue was not suitable for quantitative significance determination, so it was assessed using IMC 0609, Appendix M, and was evaluated using the qualitative criteria listed in Table 4.1. This finding was determined to be of very low safety significance because other quality assurance program functions remained unaffected by this performance deficiency, so defense-in-depth continued to exist. This issue was entered into the licensee's CAP as CR-HQN-2009-001 1 1.ATTACHMENT:

=SUPPLEMENTAL

INFORMATION=

KEY POINTS OF CONTACT

Director, Nuclear Safety Assurance System Engineering

Manager Engineering

Director Licensing

Engineer Licensing

Manager Assistant

Operations

Manager-Shift

Chemistry

Manager Operations

Manager Radiation

Protection

Manager Chemistry

Supervisor

Staff Chemist Site Vice President Maintenance

Manager

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED Failure to Manage a Yellow Risk Condition

During HPCI Testing from the Alternate

Shutdown Panel (Section 1R13)Failure to Perform Required Quality Control Inspections (Sections

4OA2)Failure to lmplement

the Experience

and Qualification

Requirements

of the Quality Assurance

Program (Section 4OA2)Opened and Closed N CV 05000 293 l 201 0005-0 1 N CV 05000 2931 201 0005-02 N CV 05000 2g3l 201 0005-03 Attachment

LIST OF DOCUMENTS

REVIEWED Section 1R04 Procedure

2.2.8, Revision 96, Standby AC Power System (Diesel Generators)

CR-PNP-2010-3735, 'A' EDG Jacket Water Temperature Switch Defective

CR-PNP-2010-3744, 'A' EDG Ventilation Damper

VD-2-8 failed in open position procedure Procedure

2.1.12.1, Attachment

1, Revision 72, Emergency Diesel Generator Surveillance

Procedure

2.2.79, Revision 39, Reactor Protection System Training Manual Diagrams of RPS Section 1R05 Procedure

5.5.2, Revision 46, Special Fire Procedure Fire Hazards Analysis , Fire Zone Data Sheet for the 'A' Residual Heat Removal Pipe Room Fire Hazards Analysis, Fire Area 1.10, Fire Zone 4.1, 'B' Train Emergency Diesel Generator Room

CR-PNP-2010-03987, Senior NRC Resident found a hose station typographical error in the Fire Hazards Analysis Fire Hazards Analysis, Fire Area 1.9, Fire Zone 3.5, Vital Motor Generator Set Room

CR-PNP-2010-3948, Rolling Fire Door in lower switchgear room did not close completely

CR-PNP-2010, 4001, hourly fire watch sheet date was wrong in lower switchgear room Procedure

8. B. 1 4, Revision 44, Fire Protection Technical Requirements

Procedure

8.8.17.1, Revision 20, Inspection of Fire Door Assemblies Fire Hazards Analysis, Fire Area 1 .10, Fire Zone 2.1 , 'B' Switchgear and Load Center Room Fire Hazards Analysis, Fire Area 1.10, Fire Zone2.11A, Turbine Deck-West End Section 1Rl1 LORTiNRC Simulator Exam Scenario,

SES-2010-06, Revision 0, Loss of Feedwater Heating with Fuel Damage accompanied by RWCU leak LORT/NRC Simulator Exam Scenario,

SES-2010-04, Revision 0, small LOCA during station blackout Section 1R12 NUMARC 93-01, Revision 2, industry guideline for monitoring the effectiveness of maintenance at nuclear power plants Procedure

EN-DC-150, Revision O, Condition Monitoring of Maintenance Rule Structures

CR-PNP-2010-3696, main breakwater stones are missing Maintenance Rule SSC Basis Document, Buildings and Structures

CR-PNP-2010-4167, unclarity in maintenance rule decisions regarding structures category Post Accident Sampling System Maintenance Rule (aX1) Action Plan Post Accident Sampling System Maintenance Rule SSC Basis Document UFSAR Chapter 10.19, Post Accident Sampling System EC23680, Evaluation of PASS Heat Trace Circuits Required for System Operation

CR-PNP-2008-2120, PASS has been declared potentially maintenance rule (aX1)due to recurring heat trace problems Attachment

EC12377, Replace H202 and PASS Health Trace System Temperature Controllers Post Accident Sampling System Drawings Post Accident Sampling System Heat Report Section 1R13 Operator's Risk Report for 1Q127110-10129110

Equipment Out-of-Service (EOOS) Tool Procedure

EN-DC-151, Revision 1, PSA Update and Maintenance

CR-PNP-2010-3860, Uncertainty with the Diesel Fire Pump being out-of-service with the

VEX-101 OOS

CR-PNP-2010-0388,

VEX-101 OOS raises the question of Diesel Fire Pump Availability Operator's Risk Report for 1111110-1112110

NUMARC 93-01, Revision 2, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Procedure

1.5.22, Revision 12, Risk Assessment Process Procedure

2.4.143, Revision 45, Shutdown from outside control room Procedure

8.5.4.6, Revision 38, HPCI Pump and Valve Operability from alternate shutdown panel Section 1R15

CR-PNP-2010-3551 , Transfer Switch Y-10 acting sluggishly when transferring back to normal power supply

CR-PNP-2O10-3735, 'A' EDG Jacket Water Temperature Switch found defective and associated operability evaluation

CR-PNP-2010-3561, 'A' EDG Jacket Water Temperature found out-of-specification

Procedure

2.1.35, Revision 51, daily rounds (EDG Room Temperature Portion) and control room readings

EN-OP-104, Revision 4, Operability Determination Process

CR-PNP-2010-3696, Main Breakwater Stones are missing in previously identified area and associated operability evaluation

CR-PNP-2007-2691, Main Breakwater Stones are missing Boston Edison Letter #79-199, to NRC, dated September

28,1979

CR-PNP-2O10-383, RHR / FPC Supports Degraded and Non-Function

CR-PNP-2O10-3621, RHR Drawing indicates

FPC pipe as non-Q versus safety-related

CR-PNP-2010-3939, Drain Valve of Moisture Separator Drain Tank not maintaining normal level Operational Decision Making lssue (ODMI) lmplementation Action Plan dated

111512010 Section 1Rl9 Work Order (WO) #00245032, Tasks 1&2, 8.Q.3.8.1, MOV Maintenance and Inspection (MO-1301-26)

CR-PNP-2O10-3479, Discovered Strain Gauge off of MO-1301-26

WO#52246521, Tasks 1&2, Stem Lube for Reactor Core lsolation Cooling (RCIC) Valves and Post Maintenance Test Procedure

8.Q.3-8.1, Revision 15, Limitorque Type HBC, SB/SMB-OO, and type

SMB-000 Valve Operator Maintenance

WO#52186868, Tasks 1-4, Line 342 CCVT Inspection and Testing Attachment

WO#52186868, Task 6, Line 342 CCt.fI Post Maintenance Test WO#52186868, Tasks 7-10, Installation of New CCVT for Line 342 and Post Maintenance Test WO#255378, Tasks 13 and 4 received spurious half scrams from RPS Channel 'B'WO#255378, Task 5, Post Maintenance Test of 'B' RPS WO#0024610601, X-107A, Replace Start Button in Panel

C-1038,'A'EDG

iaw 3.M.3-51 W0#5229362501, Train'A' Emergency Diesel Generator Surveillance

WO#00247107, Procedure

8.F.38.1, Diesel Generator Instrumental Calibration and Function Test

CR-PNP-2010-4293, Time delays found outside procedure limits

CR-PNP-2010-4313, Air Start Motor Position M2 used during testing WO#001 81 369, Replace

VSF-2068

EC-20051, Revision 0, Replace Main Stack Dilution Fans

CR-PNP-2010-4072, VSF206A tripped during VSF206B replacement

ECT-20051-01, Revision 0, functional test for

VSF-2068 Procedure

3.M.3-51, Revision 27, Electrical Termination

Procedure

3.M.3-4, Revision 55, Insulation Test Procedure

3.M.4-14, Revision 39, Rotation Equipment Inspection Assembly and Disassembly Section 1R22 WO#52287476, Task 1,8.9.1 (TS Surveillance)

EDG Train A Surveillance

Procedure

8.9.1, Revision 1 16, Emergency Diesel Generator and Associated Emergency Bus Surveillance Tech nical Specifications

CR-PNP-2010-3896, Timer

TMR1-45009, did not stop to indicate EDG start time Control Room Logs for 11l2l1o Procedure

1.3.34, Revision 117, Operations Administrative Policies and Processes, Section 6.1 0, Pre-Evolution Briefings Procedure

8.5.2.2.2, Revision 43, LPCI System LOOP B Operability-Pump Quarterly and Biennial Flow Rate Tests and Valve Tests WO#52278449, Task 1, Perform HPCI Operability Test at 1000psig Procedure

8.5.4.1, Revision 106, High Pressure Coolant lnjection (HPCI) System Pump and Valve Quarterly Operability

Procedure

9.39, Revision 0, Channel Control Blade lnterference Testing

ECH-NE-09-0056, Revision 1, PNPS Cycle 18 Channel-Control Blade Interference Monitoring Plan

CR-PNP-2010-3635, Control Rod 46-39 did not meet acceptance criteria for settle time

CR-PNP-2010-4229, Control Rod 06-39 shows indication of channel control blade interference

CR-PNP-2010-4230, unable to perform full stroke insertion testing on control rods 06-39 and 46-39 Procedure

8.5.1.1, Revision 55, Core Spray System Operability-Pump Quarterly and Biennial Comprehensive Flow Rate Tests and Valve Tests

CR-PNP-2O10-3815, Suction Pressures were inconsistent during'B'Core Spray Pump Operability Test Control Room Logs dated 1012812010

CR-PNP-2O10-4479, Resident lnspector concerns regarding the conduct of the 'B' Core Spray Pump Surveillance on 1012812010

Section 2RS01

EN-RP-101, Revision 5, Access Control for Radiological Controlled Areas

EN-RP-108, Revision 9, Radiation Protection Posting

EN-RP-121, Revision 6, Radioactive Material Control

EN-RP-131, Revision 8, Air Sampling cR-2009-04266

cR-2010-01474

cR-2009-04427

cR-2010-01541

cR-2009-04480

cR-2010-01775

cR-2010-01810

cR-2010-01761

cR-2009-04655

cR-2009-04809

cR-2009-04925

cR-2009-05298

cR-2010-00358

cR-2010-00666

cR-2010-00819

cR-2010-00923

cR-2010-00940

cR-2010-00974

cR-2010-00979

Section 2RS02

EN-RP-110, ALARA Program, Revision 7 Section 4OA1

NEI 99-02, Revision 6, Regulatory Assessment Performance Indicator Guidelines Emergency Diesel Generator System Health Report, 2O1O 3'd quarter

CR-PNP-2O10-3357, 'B' EDG Cooling Air Damper Pressure Regulator Failed NRC Performance Indicator Technique

I Data Sheets generated

4tn quarter 2009 through 3'd quarter 2010 Licensee Event Reports issued 4th quarter 2009 through 3'o quarter 2010

CR-PNP-2010-3682, during a review of MSPI data, the NRC Sr. Resident Inspector questioned the validity of the method used to account for EDG short term unavailability

MSPI Data Sheets for Cooling Water for both Reactor Building Closed Cooling Water (RBCCW) and Salt Service Water (SSW)Section 4OM Miscellaneous

CR-PNP-2009-4197, Gaps to Excellence in the lmplementation of the Maintenance Rule

CR-PNP-2010-2211, Inconsistent lmplementation of the Maintenance Rule Function Failure Determination Process Attachment Pilgrim Station Quarterly Trend Reports

CR-PNP-2010-4479, Resident lnspector concerns regarding the conduct of the 'B' Core Spray Pump Surveillance on 1012812010

EN-OP-1 04, Revision 4, Operability Determination Process

CR-PNP-2010-3815, Suction Pressures were inconsistent during'B'Core Spray Pump Operability Test EOI Letter Response to Request for lnformation, Revision 1 ENOC-10-00002

EOI Letter Response to Request for Information

ENOC-09-00037

1t8t10 11t30t10 0 through 20 1 1978 QAPM Regulatory Guide 1.8 ANSI/ANS 3.1-1978 ANSI N18.1-1971 NRC SER EOI Letter

BVY 03-12 Entergy Quality Assurance Program Manual Personnel Selection and Training American National Standard for Selection and Training of Nuclear Power Plant Personnel Quality Assurance Program Consolidation" Technical Unit Staff Qualifications Specification

5.3.1 Personnel Change Planning ChecklisVForms for QA Manager Candidates

CEO2009-00195

Corporate

ANSI Level lll Surveillance of W Maintenance American National Standard for Selection and Training of 1971 Nuclear Power Plant Personnel NRC Safety Evaluation Report, "Entergy Operations, Inc.11t6t98 various July 2QO7 12t15t2009

Inspection Program (VfY)Vermont Yankee Nuclear Power Station, Docket No. 50-271 0210512003

Annual Submittal of QAP Changes (WY)CfN-2003/00059

Vermont Yankee, 10 CFR Part 50.54(aX3)

Change Review 0412412002

EOI Letter No. Forms for QAPM Rev 8 (VfY)cNRO-2003-013

EOI Letter No. Entergy Quality Assurance Program Manual, Rev. 8 (VfY) 0412412003

cEXO-2003t164

EOf Letter NO. lssuance of Entergy Quality Assurance Program Manual 0412412003

CNRO-20021027 (OAPM) Revision 8 (WY)Attachment

cFR 50.59 Review Form ENO Letter No.1.2.02-067

EN-QV-104 Attachment

9.1 ENOC Letter NO.07-0020

AP-20.06, Attachment

MCM-4.1 Attachment

4.1

AP-20.09 Attachment Entergy Letter JLtC-02-017

ENO Letter 1.2.02-060

Entergy Letter cNRO-2002-027

CFR 50.5a(a)Evaluation

ENO Letter 1.2.02-060

ENO Meeting Summary A-7 Entergy Quality Assurance Program Manual, Revision 7 (PNPS)Entergy QA Program Manual, Revision 7 (PNPS)Entergy QA Program Manual, Revision 7 (PNPS)Independent Spent Fuel Storage lnstallation Entergy QA Program Manual Change Review Form 50.5a(a) Parts 1,2 and 3 (PLP)Entergy QA Program Manual, Revision 16, Annual Report 10

CFR 50.54(a)(3)

and10 CFR72.140(d) (PLP)FSAR Change Request Form, Relocate QA Program from Chapter 17 to Entergy QAPM (JAF)Nuclear Engineering

CFR 50.59 Screening Form (JAF)Process Applicability Screening - Relocate QA Program From FSAR Ch. 17 to Entergy QAPM (JAF)Cross Reference of QAPM commitments to lmplementing procedures at JAF Adaptation of Entergy Common QAPM, Revision 7 (JAF)Entergy QA Program Manual, Revision 7 (JAF)QA Program Change/Prior Approval Determination - Part A (rP3)Adaptation of Entergy Common QAPM, Revision 7, (lP2 and lP3)Development of Common QA Manual for northern Entergy Sites and Entergy Nuclear Generating Company Plants 04t25t2002

0510212002

07t30t2002

04.05t2007

0411512007

0510612002

04t03t2002

04t01t2002

04t02t2002

0612112002

04t25t2002

0510612002

06t21t2002

11t3012001

Enqineerinq ChanqeslMaintenance

Work Orders

ANO-EC-07032

05885 ANO-EC-02886

09121

RBS-EC-00893

RBS-EC-70734

GGN-EC-o1450

RBS-EC-02692

GGN-EC-00085

GGN-EC-01452

PLP-EC-PLP-EC-Attachment

ANO-EC-03069

2392 ANO-EC-04461

14181 ANO-EC-08043

18042 ANO-EC-00608

06553 WF3-EC-15451

2731 wF3-EC-10706

wF3-EC-o1830

wF3-EC-07960

WF3-EC-O1166

wF3-EC-09046

wF3-EC-00935

WF3-EC-01166

WF3-EC-01396

wF3-EC-01782

wF30EC-03013

wF3-EC-11284

WF3-EC-13981

Procedures

EN-Lt-121

EN-MA-102

EN-QV-1OO

EN-QV-109 EN-QV-109-02

EN-QV-129 RBS-EC-03275

RBS-EC-03643

RBS-EC-03850

RBS-EC-03275

RBS-EC-05932

RBS-EC-06947

RBS-EC-07239

RBS-EC-08504

RBS-EC-12204

RBS-EC-13128

RBS-EC-16451

RBS-EC-70752

RBS-EC-07368

RBS-EC-03852

RBS-EC-03853

RBS-EC-03975

RBS-EC-70733

GGN-EC-00224

GGN-EC-02048

GGN-EC-02058

GGN-EC-02065

GGN-EC-02107

GGN-EC-02110

GGN-EC-02201

GGN-EC-02784

GGN-EC-04538

GGN-EC-06299

GGN-EC-06301

GGN-EC-07471

GGN-EC-07716

GGN-EC-06875

GGN-EC-06039

GGN-EC-06086

GGN-EC-00494

GGN-EC-02048

GGN-EC-02065

GGN-EC-13326

GGN-EC-13354

GGN-EC-13355

ANO U-1

EC 01039 ANO U-1

EC 05808 ANO U-1

EC 13153 ANO U-1

EC 00380 ANO U-1

EC 05054 ANO U-1

EC 05388 ANO U-1

EC 06241 ANO U-1

EC 07032 ANO U-1

EC 13224 WF3-EC-844881

wF3-EC-05854

VYT-EC-O3138

PLP-EC-PLP-EC-PLP-EC-PLP-EC-PLP-EC-Entergy Trending Process Inspection Program Conduct of Nuclear Oversight Audit Process Audit Process Guidance Training and Certification of InspectionA/erification and Examination Personnel Oversight Training Program Corrective Action Requests, Supplier Stop Work Orders, and Recommendations Supplier Audits/Surveys Assessments of Nuclear Oversight?

Vulnerability Review Process Rev 8 Rev 3 and 4 Rev 4 Rev 16 Rev 0 Rev I Rev 9 Rev 6 Rev 3 Rev 2 Rev 1 CONDITION

REPORTS cR-ANO-1-2009-02330

CR-ANO-1 -2010-00743

CR-ANO-2010-01503

CR-ANO-C-2009-01884

cR-ANO-C-2009-02608

CR-AN0-2-2010-00028

cR-JAF-2008-03648

CR-HQN-2010-001

1 cR-HQN-2009-00178

cR-HQN-2009-01083

cR-HQN-2009-01084

cR-HQN-2009-01085

cR-HQN-2009-01091

cR-HQN-2009-01093

cR-HQN-2009-01096

CR-HON-2009-01

140 cR-HQN-2009-01

150

CR-HQN-2009-01

169

CR-HQN-2009-01

170

CR-HQN-2009-01

184 cR-tP2-2010-04085

cR-tP3-2010-01740

cR-tP2-2010-03985

cR-tP2-2010-03986

cR-lP2-2010-03988

cR-tP2-2010-03984

cR-rP3-2009-04903

cR-tP3-2009-04905

cR-PLP-2009-04108

cR-PLP-2009-05613

cR-PLP-2009-05918

cR-PLP-2009-05908

cR-PNP-2009-01798

cR-PNP-2009-02059

cR-PNP-2009-02255

cR-PNP-2008-00916

cR-RBS-2008-04685

CR-RB3-2009-05041

CR-RBS-2009-06123

A_9

CR-ANO-1 -2010-01724

CR-ANO-1 -2010-01182

cR-JAF-2009-04592

cR-HQN-2009-01

188 cR-HQN-2009-01

197 CR-HQN-2010-00013

cR-HQN-2010-00386

cR-HQN-2010-00571

CR-HQN-2010-00593

cR-HQN-2010-00515

cR-HQN-2010-00550

CR-HQN-2010-0051

cR-HQN-2010-00510

cR-HQN-2010-00475

cR-HQN-2010-00499

cR-HQN-2010-00338

cR-tP3-2009-04917

cR-lP3-2009-04920

cR-tP3-2009-04897

cR-tP2-2009-05404

cR-tP2-2009-05409

cR-tP3-2009-04868

cR-rP3-2009-04883

cR-rP3-2009-04884

cR-PLP-2010-02288

cR-PLP-2010-02290

cR-PLP-2009-05942

cR-PNP-2008-03922

cR-PNP-2009-05359

CR-PNP-2010-00015

cR-RBS-2010-01472

CR-RBS-2010-02033

CR-RBS-2010-00200

CR-ANO-1-2010-01080

CR-ANO-1 -2010-00719

CR-JAF-2010-03280

CR-HON-2010-00415

cR-HQN-2010-00333

cR-HQN-2010-00123

cR-HON-2010-00109

cR-HQN-2010-00068

cR-HQN-2010-00063

cR-HQN-2010-00045

cR-HQN-2010-00060

CR-HQN-2009-01

198

CR-HQN-2009-01

194 cR-HQN-2010-00594

oR-HQN-2009-01

171

CR-HQN-2009-01

153 cR-tP2-2009-05393

cR-rP2-2009-05399

cR-tP2-2009-05400

cR-tP2-2009-05389

cR-tP2-2009-05349

cR-rP2-2009-05348

cR-lP2-2009-05321

cR-PLP-2009-05909

cR-PLP-2010-02012

cR-PLP-2009-05897

cR-PNP-2009-05303

cR-PNP-2009-05297

cR-PNP-2010-02124

cR-RBS-2010-00006

cR-RBS-2009-06472

cR-RBS-2009-06495

cR-RBS-2009-06446

cR-RBS-2009-06451

cR-RBS-2009-06471

cR-RBS-2009-06473

cR-RBS-2009-06490

CR-RBS-2O10-00044

cR-wF3-2010-01

198 cR-wF3-2010-01356

cR-wF3-2010-00746

cR-wY-2009-04496

cR-wY-2O10-01479

cR-wY-2O10-02759

CR-GGN-2010-04140

cR-GGN-2010-02730

CR-GGN-2010-04178

CR-GGN-2010-04101

cR-GGN-2010-04092

cR-GGN-2010-03674

cR-GGN-2010-03721

CR-GGN-2010-03900

cR-cGN-2010-03451

CR-GGN-2010-03492

CR-ANO-1-2009-02330

cR-RBS-2010-00221

CR-RBS-2o10-00278

cR-RBS-2010-00088

CR-RBS-2010-0001

cR-RBS-2009-06520

cR-RBS-2009-06539

cR-wF3-2010-00284

cR-wF3-2009-07713

cR-wY-2o10-04432

cR-wY-2010-04434

cR-GGN-2010-02135

cR-GGN-2010-02382

cR-GGN-2010-02902

cR-GGN-2010-00590

cR-GGN-2010-01247

cR-GGN-2010-01252

cR-GGN-2009-06575

cR-GGS-2009-06907

cR-GGS-2009-06920

CR-ANO-2o10-01503

cR-RBS-2009-06456

cR-RBS-2009-06450

cR-RBS-2009-06452

cR-RBS-2009-061s8

cR-RBS-2009-06209

cR-RBS-2009-06449

cR-wF3-2009-07711

cR-wF3-2010-02629

cR-wY-2o10-04496

cR-wY-2o10-00070

cR-GGS-2009-06921

cR-GGS-2009-06922

cR-GGS-2009-06923

cR-GGS-2009-06927

cR-GGS-2009-06806

cR-GGN-2010-00164

cR-GGN-2009-06904

cR-GGN-2009-06910

cR-GGN-2009-06505

CR-ANO-1 -2010-00743

ADAMS ALARA ASP CFR CR DRP DRS EDG HPCI tMc MRP NCV NEI NRC PI PNPS RP RPM RPS RWP's SSC TIP VHRA WO A-11

LIST OF ACRONYMS

Agencywide

Documents

Access and Management

System As Low As Reasonably

Achievable

Alternate

Shutdown Panel Code of Federal Regulations

Condition

Report Division of Reactor Projects Division of Reactor Safety Emergency

Diesel Generator High Pressure Coolant Injection Inspection

Manual Chapter Maintenance

Rule Program Non-Cited

Violation Nuclear Energy lnstitute Nuclear Regulatory

Commission

Performance

Indicator Pilgrim Nuclear Power Station Radiation

Protection

Radiation

Protection

Manager Reactor Protection

System Radiation

Work Permit(s)Structure, System or Component Traversing

ln-Core Probe Very High Radiation

Area Work Order Attachment

@@ Line 121: / Line 121: @@
 ===.12 Q)Inspection===
-Scope (2 samples)The inspectors reviewed the two samples listed below for items such as: (1) appropriate work practices; (2) identifying and addressing common cause failures; (3) scoping in accordance with 10 CFR 50.65 paragraph (b) of the Maintenance Rule; (4) characterizing reliability issues for performance; (5) trending key parameters for condition monitoring; (6)charging unavailability for performance; (7) classification and reclassification in accordance with 10 CFR 50.65 paragraph (aX1) or (aX2); and (8) appropriateness of performance criteria for structures, systems, and components (SSCs)/functions classified as paragraph (aX2) and/or appropriateness and adequacy of goals and corrective actions for SSCs/functions classified as paragraph (aX1). The documents reviewed during this inspection are listed in the Attachment.
+Scope (2 samples)The inspectors reviewed the two samples listed below for items such as:
+: (1) appropriate work practices;
+: (2) identifying and addressing common cause failures;
+: (3) scoping in accordance with 10 CFR 50.65 paragraph
+: (b) of the Maintenance Rule;
+: (4) characterizing reliability issues for performance;
+: (5) trending key parameters for condition monitoring; (6)charging unavailability for performance;
+: (7) classification and reclassification in accordance with 10 CFR 50.65 paragraph (aX1) or (aX2); and
+: (8) appropriateness of performance criteria for structures, systems, and components (SSCs)/functions classified as paragraph (aX2) and/or appropriateness and adequacy of goals and corrective actions for SSCs/functions classified as paragraph (aX1). The documents reviewed during this inspection are listed in the Attachment.
 ltems reviewed included the following:

IR 05000293/2010005: Difference between revisions

Revision as of 23:56, 18 September 2018

Text

Dear Mr. Smith:

Enclosure:

Attachment:

SUMMARY OF FINDINGS

Cornerstone: Mitigating

REPORT DETAILS

.04 O)a. Inspection

.10 , Fire Zone 2.1, 'B' Switchgear

1R11 Licensed Operator Requalification

1R12 Maintenance

.12 Q)Inspection

.13 )a. Inspection

a. Inspection Scope

.19 )a. Inspection

1R22 Surveillance

2. RADTATTON

a. Inspection Scope

a. Inspection Scope

.2 15 Cornerstone:

.3 a.

Introduction:

a. Inspection Scope

KEY POINTS OF CONTACT

LIST OF ITEMS

LIST OF DOCUMENTS

Procedure

Procedure

Procedure

Procedure

Procedure

Procedure

Work Orders

Procedures

LIST OF ACRONYMS

Navigation menu

IR 05000293/2010005: Difference between revisions

Revision as of 23:56, 18 September 2018

Text

Dear Mr. Smith:

Enclosure:

Attachment:

SUMMARY OF FINDINGS

Cornerstone: Mitigating

REPORT DETAILS

.04 O)a. Inspection

.10 , Fire Zone 2.1, 'B' Switchgear

1R11 Licensed Operator Requalification

1R12 Maintenance

.12 Q)Inspection

.13 )a. Inspection

a. Inspection Scope

.19 )a. Inspection

1R22 Surveillance

2. RADTATTON

a. Inspection Scope

a. Inspection Scope

.2 15 Cornerstone:

.3 a.

Introduction:

a. Inspection Scope

KEY POINTS OF CONTACT

LIST OF ITEMS

LIST OF DOCUMENTS

Procedure

Procedure

Procedure

Procedure

Procedure

Procedure

Work Orders

Procedures

LIST OF ACRONYMS

Navigation menu

Search