ML14314A783
| ML14314A783 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/08/1999 |
| From: | Brian Bonser NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Young D CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 9910210171 | |
| Download: ML14314A783 (22) | |
Text
October 8, 1999 Carolina Power & Light Company ATTN:
Mr. D. E. Young Vice President H. B. Robinson Steam Electric Plant Unit 2 3581 West Entrance Road Hartsville, SC 29550
SUBJECT:
MID-CYCLE PLANT PERFORMANCE REVIEW (PPR) - H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2
Dear Mr. Young:
On September 30, 1999, the NRC staff completed the mid-cycle Plant Performance Review (PPR) of H. B. Robinson Steam Electric Plant Unit 2. The staff conducted these reviews for all operating nuclear power plants to integrate performance information and to plan for inspection activities at your facility over the next five months. The focus of this performance review was to identify changes in performance over the past six months, and to allocate inspection resources accordingly.
We did not identify any areas in which your performance warranted more than the core inspection program. Based on this review, we plan to conduct only core inspections at your facility over the next five months. contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated review of licensee performance trends. The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and Carolina Power and Light Company from October 1, 1998, to September 30, 1999. As noted above, greater emphasis was placed on those issues identified in the past six months during this performance review. The NRC does not attempt to document all aspects of licensee programs and performance that may be.
functioning appropriately. Rather, the NRC only documents issues that the NRC believes warrant management attention or represent noteworthy aspects of performance. In addition, the PPR may also have considered some predecisional and draft material that does not appear in the attached PIM, including observations from events and inspections that had occurred since the last NRC inspection report was issued, but had not yet received full review and consideration. Once this predecisional material is finalized it will be placed in the Public Document Room (PDR) as part of normal issuance of NRC inspection reports and other correspondence.
This letter advises you of our plans for future inspection activities at your facility so that you will have an opportunity to prepare for these inspections and to provide us with feedback on any planned inspections that may conflict with your plant activities. Enclosure 2 details our inspection plan through March 2000 to coincide with the scheduled implementation of the revised reactor oversight process in April 2000. The rationale or basis for each inspection outside the core inspection program is discussed above so that you are aware of the reason for emphasis in these program areas. Routine resident inspections are not listed due to their ongoing and continuous nature.
9910210171 991008 PDR ADOCK 05000261 G
CP&L 2
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Brian R. Bonser at (404) 562-4560 with any questions you may have.
Sincerely, (Original signed by B. R. Bonser)
Brian R. Bonser, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No. 50-261 License No. DPR-23
Enclosures:
- 1. Plant Issues Matrix 2 Inspection Plan cc w/encls: (See page 3)
CP&L 3'
cc w/encls:
J. W. Moyer William D. Johnson Director, Site Operations Vice President & Corporate Secretary Carolina Power & Light Company Carolina Power & Light Company H. B. Robinson Steam Electric Plant Electronic Mail Distribution Electronic Mail Distribution John H. O'Neill, Jr.
T. D. Walt Shaw, Pittman, Potts & Trowbridge Plant General Manager 2300 N. Street, NW Carolina Power & Light Company Washington, DC 20037-1128 H. B. Robinson Steam Electric Plant Electronic Mail Distribution Peggy Force Assistant Attorney General Terry C. Morton, Manager State of North Carolina Performance Evaluation and Electronic Mail Distribution Regulatory Affairs CPB 9 Electronic Mail Distribution Robert P. Gruber Executive Director H. K. Chernoff, Supervisor Public Staff - NCUC Licensing/Regulatory Programs P. 0. Box 29520 Carolina Power & Light Company Raleigh, NC 27626-0520 H. B. Robinson Steam Electric Plant Electronic Mail Distribution Public Service Commission State of South Carolina R. L. Warden, Manager P. 0. Box 11649 Regulatory Affairs Columbia, SC 29211 Carolina Power & Light Company H. B. Robinson Steam Electric Plant Distribution w/encls: (See page 4)
Electronic Mail Distribution Virgil R. Autry, Director Div. of Radioactive Waste Mgmt.
Dept. of Health and Environmental Control Electronic Mail Distribution R. Mike Gandy Division of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution Mel Fry, Director Division of Radiation Protection N. C. Department of Environment, Health and Natural Resources Electronic Mail Distribution
CP&L 4
Distribution w/encls:
S. Collins, NRR J. Zwolinski, NRR W. Dean, NRR T. Boyce, NRR C. Thomas, NRR R. Subbaratnam, NRR J. Yerokun, Regional Coordinator, EDO J. Lieberman, OE B. Bonser, RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 2112 West Old Camden Road Hartsville, SC 29550 OFFICE DRP/RII DRS/RII DRS/RII DRS/RII DRS/R I_
SIGNATURE GMacDonald:vg rr HChfspqisen isle KL NAME MOW DATE 10/ L 199 10/ 0 199
/99 0/
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/99 10/
/99 COPY?
eES NO
&ES )
NO YES NO ES NO YES NO YES NO YES NO OFFICIAL RECORD COPY CUMENT NA
- \\ROBINSO PR\\99Q3\\pp w
Page:
1 of 17SttsC m i io 1/07/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 08/14/1999 1999005-01 Pri: OPS NRC URI Prl: 1A Service Water Temperature Notice Of Enforcement Discretion Sec:
Sec:
The licensee requested and received a Notice of Enforcement Discretion (NOED) related to Technical Specifications (TS) service water (SW) temperature limits. SW temperature exceeded TS limits during a period of Dockets Discussed:
Ter:
sustained hot weather. The NOED allowed continued unit operation.
05000261 ROBINSON 2 07/30/1999 1999301 Pri: OPS NRC NEG Pri: IC Examination Results Sec:
Sec:
Four of seven (57%) applicants passed the examination. All of the SRO applicants passed. All of the RO applicahts Dockets Discussed:
Ter:
failed the written examination. One of the RO applicants failed the operating test as well.
05000261 ROBINSON 2 07/30/1999 1999301 Pri: OPS NRC POS Pri: iC Operator Licensing Exam Sec:
Sec; The as-submitted wrtten examination and operating tests met the gidelines of NUREG-1021.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 07/03/1999 1999004 Pri: OPS NRC POS Pri: 1A New Fuel Inspections Sec:
Sec:
New fuel inspections were performed in accordance with the licensee's procedures. The required fuel inspections Dockets Discussed:
were performed and documented by a reactor engineer. Foreign material exclusion procedures were correctly Dockts Dscused:Ter.
implemented.
05000261 ROBINSON 2 07/03/1999 1999004 Pri: OPS NRC POS Pr: 1A Moderator Temperature Coefficient Sec:
Sec:
Measurement of the end of life moderator temperature coefficient (MTC) was performed in accordance with licensee procedures. Plant maneuvers were conservative with respect to reactivity addition. There were no discrepancies W
Dockets Discussed:
Ter:
noted with the acquisition of the data and the calculation of the MTC.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: OPS NRC MISC Pri: 2A Housekeeping / Temporary Material Storage Sec:
Sec:
Overall plant housekeeping was found to be maintained in accordance with licensee procedures. The licensee's plant housekeeping procedure was noted to have some confusing guidelines with regard to temporary material Dockets Discussed:
Ter:
storage. The licensee plans to resolve the concern through the condition report process.
05000261 ROBINSON 2 Item Type (ComplianceFollowupOther), From 09/11/1998 To 09/30/1999
Page: 2 of 17UntdN cer D
4 C m iso 10/07/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes item Description 05/22/1999 1999003 Pri: OPS NRC NEG Pri: 3A Equipment-Out-Of-Service Program Sec:
Sec: 1A The Equipment-Out-Of-Service (EOOS) program had not been utilized in the scheduling of work activities for a week contrary to recommendations in the licensee's procedures. The EOOS program graphically illustrates the change in Dockets Discussed:
Ter:
core damage frequency when equipment is taken out-of-service. An acceptable level of risk was ensured by utilizing 05000261 ROBINSON 2 the matrix of safety significant combinations as presented in the work coordination procedure.
05/22/1999 1999003 Pri: OPS NRC POS PrI: 1A Plant Operations Sec:
Sec:
The conduct of operations was professional, risk informed, and safety-conscious.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 05/22/1999 1999003 Pr: OPS NRC POS Pri: 1A Power Reductions Sec:
Sec:
Two power reductions conducted during the report period were well planned and executed. Effective communications were maintained between operations personnel. Technical Specification limiting conditions for Dockets Discussed:
Ter:
operation were met throughout the evolutions.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: OPS NRC POS Pri: 2A System Walkdown Sec:
Sec: 1C A system walkdown found that the Post Accident Containment Ventilation System and the Isolation Valve Seal Water System were appropriately configured and maintained. System parameters were being maintained within Dockets Discussed:
Ter:
Technical Specification requirements.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: OPS NRC POS Pri: 1A Clearance Review Sec: MAINT Sec:
A clearance associated with a safety injection pump breaker inspection provided adequate isolation conditions for personnel safety and protection of plant equipment. The clearance was implemented in accordance with the Dockets Discussed:
Ter:
licensee's procedures.
05000261 ROBINSON 2 04/10/1999 1999002 Pri: OPS NRC NEG Pri: 1A Radiation Monitor Setpoint Verification Sec:
Sec: 3A A discrepancy between the Reactor Turbine Generator Board indication and the radiation monitoring system recorder indication for the letdown radiation monitor was observed. Operators exhibited inattention to detail in not Dockets Discussed:
Ter:
recognizing the discrepancy.
05000261 ROBINSON 2 Item Type (Compliance, FollowupOther), From 09/11/1998 To 09/30/1999
Page: 3 of17 U ie ttsC m iso 10/07/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template item Title Date Source Area ID Type Codes Item Description 04/10/1999 1999002 Pr: OPS NRC POS Pri: 1A Walkdown of Important Field Operator Actions Sec:
Sec: 3B A walkdown of the important field operator actions identified by the Probabilistic Safety Analysis determined that the operator was knowledgeable and that necessary equipment was appropriately staged to perform necessary tasks in Dockets Discussed:
Ter:
a timely manner.
05000261 ROBINSON 2 04/10/1999 1999002 Pri: OPS NRC POS Pri: IC Tracking and Resolution of Operator Work Arounds Sec:
Sec:
The licensee had established adequate procedural guidance for the identification, tracking and resolution of Dockets Discussed:
Ter:
Operator Workarounds (OWA). One new OWA was identified that had not been identified by the licensee.
05000261 ROBINSON 2 04/10/1999 1999002 Pri: OPS NRC POS Pri: 1C Operator Work Arounds Effect On Component Reliability Sec:
Sec:
The inspectors did not identify any reduction in system or component reliability or availability due to Operator Work Arounds or compensatory measures. The simulator and training staff were adequately maintaining the simulator like Dockets Discussed:
Ter:
the plant and also were incorporating modeling changes necessary to mimic the actual plant deficiencies.
05000261 ROBINSON 2 04/10/1999 1999002 Pri: OPS NRC POS Pri: IC Cummulative Effect of Operator Work Arounds Sec:
Sec: 5A Except for one example, the licensee effectively identified OWAs, established reasonable corrective actions, and satisfactorily assessed OWAs for overall cumulative effect on safe operations of the plant. The recent Dockets Discussed:
Ter:
self-assessments dealing with OWAs were thorough, detailed, and self-critical. Senior site management routinely 05000261 ROBINSON 2 reviewed the results of the OWA cumulative assessments and were aware of ongoing problems, compensatory measures, and scheduled corrective actions.
02/27/1999 1999001 Pri: OPS NRC NEG Pri: 1C Requalification Program Sec:
Sec:
The majority of the biennial written examination questions met the guidelines of NUREG-1021, Examiner Standards ocksDiscussed:
T and facility training procedures. Some of the written operator licensing examination questions contained DocketsTer:
psychometric flaws which diminished their effectiveness in evaluating operator knowledge. Overall the examination 05000261 ROBINSON 2 was considered valid.
02/27/1999 1999001 Pr: OPS NRC POS Pr: 1A Auxiliary.Feedwater Walkdown Sec:
Sec:
A system walkdown found that the auxiliary feedwater system was appropriately aligned, component labeling and housekeeping were adequate.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 Item Type (ComplianceFollowupOther), From 09/11/1998 To 09/30/1999
Page: 4 of 17 11/1949 1:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 02/27/1999 1999001 Pri: OPS NRC POS Pri: 1C Requalification Program Sec:
Sec:
The conduct and performance of the simulator examinations were satisfactory. The facility evaluators were thorough in noting individual performance discrepancies and the scenarios observed were effective in determining Dockets Discussed:
Ter:
areas in need of retraining. Job performance measures adequately tested operators ability to perform tasks using 05000261 ROBINSON 2 the licensee's procedures. The licensee conducted remedial training and evaluations as required by 10 CFR 55.59 and facility training procedures. Operators that had failed requalification tests and quizzes were removed from shift until remediation was complete.
01/16/1999 1998012 Pri: OPS Licensee MISC Pri: 1C Service Water Notice Of Enforcement Discretion Sec:
Sec: 5A The licensee aproached the Ultimate Heat Sink temperature limit during the Summer of 1998. A Notice of Enforcement Discretion (NOED) and an exigent Technical Specification (TS) amendment were granted to extend the Dockets Discussed:
Ter:
TS action time. The licensee never exceeded the temperature limit and did not use the extra action statement time 05000261 ROBINSON 2 allowed by the NOED and the TS amendment.
01/16/1999 1998012 Pri: OPS Licensee NEG Pri: 3A Non-Safety Related Human error Sec:
Sec:
A human error in not using existing procedural guidance to perform a valve line-up on a non-safety related system Dockets Discussed:
-Ter:
resulted in water intrusion into the "A" Emergency Diesel Generator (EDG) room. EDG operability was not affected.
05000261 ROBINSON 2 01/16/1999 1998012 Pri: OPS NRC POS Pri: 1A Maintenance Outage Operations Performance Sec:
Sec:
Operations perfomance during shutdown and startup activities for a maintenance outage was well planned and Dockets Discussed:
Ter:
executed and error free.
05000261 ROBINSON 2 01/16/1999 1998012 Prl: OPS NRC POS Pr: IC Licensee Overtime Sec:
Sec:
A review of licensee overtime during refueling outage 18 concluded that the licensee was meeting requirements.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 01/16/1999 1998012 Pri: OPS NRC POS PrI: 1C Electronic Logkeeping Sec:
Sec:
The recent transition to electronic logkeeping was well planned and operators were given sufficient training before Dockets Discussed:
Ter:
implementation.
05000261 ROBINSON 2 Item Type (Compliance FollowupOther), From 09/11/1998 To 09/30/1999
Page:
5 of 17 10/07/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 12/05/1998 1998011 Pri: OPS NRC POS Pri: 1A Safety Injection System Walkdown Sec:
Sec: 2A A detailed system walkdown found that the Safety Injection System was appropriately configured to perform its Dockets Discussed:
Ter:
design function.
05000261 ROBINSON 2 12/05/1998 1998011 Pri: OPS NRC POS Pri: 1C Plant Nuclear Safety Committee Sec:
Sec:
The onsite review functions of the Plant Nuclear Safety Comittee (PNSC) were conducted in accordance with Dockets Discussed:
Ter:
Technical Specifications. During the PNSC meetings topics were thoroughly discussed and evaluated.
05000261 ROBINSON 2 12/05/1998 1998011 Pri: OPS NRC POS Pri: iC Cold Weather Preparations Sec:
Sec: 2A The licensee program for cold weather protection was adequately implemented. Freeze protection panels and circuits, as well as, temporary enclosures and heaters were appropriately installed and maintained per procedure.
Dockets Discussed:
Ter: 28 05000261 ROBINSON 2 12/05/1998 1998011 Pri: OPS NRC POS Pri: 1C Clearance Review Sec: MAINT Sec:
A clearance associated with a charging pump was correctly implemented. A review of existing clearances identified that clearances older than three months had been evaluated in accordance with licensee procedures and did not Dockets Discussed:
Ter:
impact plant safety.
05000261 ROBINSON 2 10/24/1998 1998009 Pri: OPS NRC NEG Pri: 3A Operator Inattention to Detail Sec:
Sec:
Two examples of operator inattention to detail were identified involving operators not recognizing a failed Emergency Dockets Discussed:
Response Facility Information System printer and the subsequent missed review of plant parameters; and Ter:
documentation completeness during an emergency diesel generator surveillance.
05000261 ROBINSON 2 10/24/1998 1998009 Prl: OPS NRC POS Pri: 18 Reactor Trip Response and Evaluation Sec:
Sec: 58 Operator response to a turbine trip and automatic reactor trip was appropriate and in accordance with procedures.
The licensee's event review was thorough and the findings identified the root causes of the event. The licensee Dockets Discussed:
Ter:
appropriately generated Condition Reports to track planned corrective actions.
05000261 ROBINSON 2 Item Type (ComplianceFollowup Other), From 09/11/1998 To 09/30/1999
Page: 6 of 17SttsN cerC m i io 10/0711999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region 11 ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 10/24/1998 1998009 Pri: OPS NRC POS Pri: IC Simulator Examinations Sec:
Sec:
Simulator examinations observed demonstrated the effectiveness of licensed operator requalification training.
Simulator examination scenario guides were well developed and detailed. Operator performance was effectively Dockets Discussed:
Ter:
assessed by the training department.
05000261 ROBINSON 2 10/24/1998 1998009 Pri: OPS NRC POS Pri IC Measuring & Test Equipment Program SeC MAINT S*c A Maite-ance and Test Equipment (MATE) program review concluded that the program met the requirements of ot Urdated F ina Safety Analysis Report (UFSAR) and was implemented in accordance with procedural Dockets Discussed:
Tmt Out of tolerance MATE was identified and applicable procedure steps were reperformed with 05000261 ROBINSON 2 anrornately calibrated test equipment The M&TE calibration laboratory personnel were knowledgeable of program requr,ermts M&TE calibration history, calibration requirements and frequency, and the basis for the program were wet maintained 09/12/1998 1998008 Pri: OPS Licensee NEG Prt: 2A Two configuration control issues Sec:
Sec: 5A Two components were found to be out of their normal position. Appropriate corrective actions were taken to restore Dockets Discussed:
Ter:
these components to their normal configuration. The safety significance for both these events was minimal.
05000261 ROBINSON 2 09/12/1998 1998008 Pri: OPS NRC POS Pri: 1A Hurricane Bonnie Sec: PLTSUP Sec:
The licensee took appropriate measures to prepare the site for adverse weather conditions in anticipation of Dockets Discussed:
Ter:
Hurricane Bonnie.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: MAINT NRC POS Pri: 3A Maintenance Activities Sec:
Sec:
Maintenance activities were conducted in accordance with applicable work documents and procedures. Personnel Dockets Discussed:
Ter:
were properly trained and knowledgeable of their assignments.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: MAINT NRC POS Pri: 3A Surveillances Sec:
Sec:
A review of completed surveillance test packages demonstrated acceptable test results.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 Item Type (ComplianceFollowupOther), From 09/11/1998 To 09/30/1999
Page: 7 of17 Sae 10107/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 04/10/1999 1999002-01 Pri: MAINT NRC NCV Pri: 3A Failure To Follow Procedures During Safety Related Breaker Maintenance Sec:
Sec: 3B Preventive maintenance on the "B" containment spray pump breaker was performed by knowledgeable electricians.
A violation was identified involving an electrician's failure to follow the preventive maintenance procedure during Dockets Discussed:
Ter:
annunciator checks of the breaker.
05000261 ROBINSON 2 02/27/1999 1999001 Pri: MAINT NRC POS Pri: 2B Pressure Isolation Valve Maintenance/Testing Sec:
Sec:
The program for maintenance and testing of pressure isolation valves (PIVs) satisfied Technical Specification requirements. Leakage testing of two PIVs was not required and not included in the licensee's in-service testing Dockets Discussed:
Ter:
program. There were no examples of inadequate maintenance or examples that would indicate an adverse trend or 05000261 ROBINSON 2 degradation in the material condition of reactor coolant system PIVs. Review of leakage testing data indicated good material condition of these isolation boundaries.
02/27/1999 1999001 PrI: MAINT NRC POS Pri: 2B Relief Valve Testing Sec:
Sec:
The program for testing of ASME Section XI Class 2 and 3 relief valves met requirements. The initiatives for increased testing frequency of certain relief valves demonstrated a positive safety culture.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 01/16/1999 1998012 Pri: MAINT NRC POS Pri: 3A Maintenance Performance Sec:
Sec:
Licensee actions to repair a weld leak in the Chemical and Volume Control System were well managed and coordinated between Operations, Engineering and Maintenance. Operability determinations were thorough and Dockets Discussed:
Ter:
conservative. Repairs were performed in accordance with procedures. One concern was identified with regard to 05000261 ROBINSON 2 the staging of a wooden plug required for loss of freeze seal contingency plans.
12/05/1998 1998011 Pri: MAINT NRC POS Pri: 5A Reactor Coolant System Flow Transmitter Tubing Leak Sec:
Sec: 5B Licensee response and actions with regard to a Reactor Coolant System (RCS) flow transmitter tubing fitting leak were conservative and technically sound. Compensatory measures were instituted to monitor the leak until a W
Ter: 2A shutdown repair can be made. There were no operability concerns identified and the RCS leak was within TS leak 05000261 ROBINSON 2 rate Imits.
12/05/1998 1998011 Pri: MAINT NRC POS Prl: 3A Emergency Diesel Generator Fuel Oil Testing Sec: OPS Sec: 2B During an EDG fuel oil system flow test, the reactor operator performing the test exhibited a good questioning attitude by identifying a procedural step that would have rendered both EDGs inoperable. The procedural Dockets Discussed:
Ter: 3B deficiency was not recognized by procedure writers and reviewers or by operators during a pre-surveillance briefing.
05000261 ROBINSON 2 Item Type (ComplianceFollowup Other), From 09/11/1998 To 09/30/1999
Page: 8 of 17 10/0711999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 10/24/1998 1998009-01 Pri: MAINT Licensee NCV Pri: 2B Missed Technical Specification Required Surveillance For Valve Position Verification Sec:
Sec:
A Non-Cited Violation was identified involving two inadequate Technical Specification required surveillance Dockets Discussed:
Tr procedures involving valve position verification. The affected valves were verified to be in their required position.
De Ter.
Licensee corrective actions were appropriate.
05000261 ROBINSON 2 09/12/1998 1998008 Pri: MAINT Licensee NEG Pri: 3A CCW Valve Stroke Time Increase Sec:
Sec:
The inspectors concluded that the licensee had demonstrated that valve CC-749A was not degraded. The increased stroke time previously experienced was apparently the result of a measurement error. The retesting of Dockets Discussed:
Ter:
valve CC-749A could have been performed in a more timely manner.
05000261 ROBINSON 2 08/14/1999 1999005 Pri: ENG NRC NEG Pri: 4A Containment Air Temperature Sec:
Sec:
The licensee adequately maintained the containment bulk air temperature within design limits. Two discrepancies Dockets Discussed:
associated with a design calculation and a modification package were identified by the inspectors and corrected by Dockts Dscused:Ter:
the licensee.
05000261 ROBINSON 2 08/14/1999 1999005-02 Pri: ENG Licensee NOV Pri: 4C Inadequate Procedures for Obtaining American Society of Mechanical Engineers Code Required Vibration Da Sec:
Sec:
An operability determination for the charging pumps addressed the appropriate technical concerns and was Dockets Discussed:
performed in accordance with the licensee's procedures. The predictive maintenance engineer displayed a good Ter:
questioning attitude discovering the discrepancy. A violation was identified that involved inadequate procedures for 05000261 ROBINSON 2 obtaining the required pump vibration data specified by the ASME code.
08/14/1999 1999005 Pri: ENG NRC POS Pri: 4B Emergency Diesel Generator Operability Evaluation Sec: OPS Sec:
An engineering service request addressing the operability of the B emergency diesel generator (EDG) following the Dockets Discussed:
breaking of one of the three drive belts for the room supply fan utilized conservative assumptions and was consisten Ter:
with the methodology used in the current design calculations. The B EDG was determined to be operable with the 05000261 ROBINSON 2 belt broken.
07/03/1999 1999004 Pri: ENG NRC NEG Pri: 5C Safety Injection Accumulator Level Transmitter Sec:
Sec:
Corrective actions taken to resolve safety injection accumulator level transmitter LT-930 inaccuracy involved Dockets Discussed:
numerous maintenance attempts over a two month period indicating poor problem resolution. While cross checking Ter:
the operable accumulator level instrument LI-928, with other parameters showed that this instrument channel was 05000261 ROBINSON 2 functional, the licensee could have provided greater assurance of LI-928 accuracy by performing a calibration early in the corrective action process.
Item Type (Compliance,FollowupOther), From 09/11/1998 To 09/30/1999
Page: 9 of 17SttsC m i io 10/0711999 1513:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template item Title Date Source Area ID Type Codes Item Description 07/03/1999 1999004 Pri: ENG NRC POS Pri: iC Design Change Control Procedures Sec:
Sec:
The licensee's design change control procedures complied with the requirements of 10 CFR 50.59, and 10 CFR 50, Dockets Discussed:
Ter:
Appendix B, Criterion III, and ANSI N45,2.11-1974.
05000261 ROBINSON 2 07/03/1999 1999004 Pr: ENG NRC POS Pri IC Year 2000 Review Sec S*C A yeaf '0 (Y2K) readiness program review was completed. Overall the Y2K project is about 98 percent complete and ?to comtm'gen"c pian is about 95 percent complete. Both programs were on target to be completed by their Dockets Discussed:
o*,
sc'ed.Ied due daes 05000261 ROBINSON 2 07/03/1999 1999004 Pr: ENG NRC POS Prt 4B Containment Liner Inspection Sec:
Sec: IC The licensee's procedure for inspection of the containment liner incorporated current regulatory requirements.
Engineering provided good support to the plant to effectively implement industry experience with liner corrosion Dockets Discussed:
Ter:
issues and prepare to implement the requirements of Article IWE of ASME Section XI.
05000261 ROBINSON 2 07/03/1999 1999004 Pri: ENG NRC POS Pri: 5A Engineering Self-Assessments Sec:
Sec: 5B The self-assessments performed within the Robinson Engineering Support Section (RESS) were effective in Dockets Discussed:
Ter:
identifying engineering performance deficiencies and were useful in providing oversight to management.
05000261 ROBINSON 2 07/03/1999 1999004-01 Pri: ENG NRC NCV Pri: 4A Failure To Follow Design Control Procedures Sec:
Sec:
Plant modification packages were technically adequate with some exceptions. The 10 CFR 50.59 safety evaluation, design inputs, design evaluations, assumptions and references, and installation instructions generally met regulatory Dockets Discussed:
Ter:
requirements. Six examples of a violation were identified for failure to follow design control procedures.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: ENG NRC POS Pr: 4A North Service Water Header Modification Sec:
Sec:
A 10 CFR 50.59 screening and Unreviewed Safety Question determination for the modification of the north service water header included the appropriate design considerations and was performed in accordance with the licensee's Dockets Discussed:
Ter:
procedure.
05000261 ROBINSON 2 Item Type (ComplianceFollowup.Other), From 09/11/1998 To 09/30/1999
Page:
10 of 17
'10/071199915:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region 11 ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 04/10/1999 1999002 Pri: ENG NRC NEG Pr: 4B Operability Evaluation for "A" Emergency Diesel Generator Sec:
Sec:
Weaknesses in the operability evaluation associated with an emergency diesel generator lube oil leak were identified. The root cause analysis performed by the licensee associated with the lube oil gasket failure was Dockets Discussed:
Ter:
thorough and resulted in appropriate corrective actions.
05000261 ROBINSON 2 01/16/1999 1998012 Pri: ENG NRC POS Pri: 4A Temporary Modification Sec:
Sec:
A temporary modification to jumper a portion of the "A" reactor coolant pump oil reservoir level limit switch was Dockets Discussed:
comprehensive and in accordance with procedures. The temporary modification provided the compensatory action W Ter:
for the degraded condition and restored the associated control room annunciator.
05000261 ROBINSON 2 12/05/1998 1998011-03 Pri: ENG NRC NEG Pri: 2A Dedicated Shutdown Emergency Diesel Generator Governor Speed Droop Setting Sec:
Sec:
The inspectors noted inconsistencies with the actual dedicated shutdown diesel generator governor speed droop Dockets Discussed:
setting and the setting described in the system description and vendor manual. The safety significance was minimal Ter:
as an operator is stationed at the diesel control panel during station blackout to control frequency. The system 05000261 ROBINSON 2 engineer appropriately initiated a condition report to revise procedures to reflect vendor recommendations.
10/24/1998 1998009 Pri: ENG NRC POS Pri: 48 Engineering Support Sec:
Sec:
Engineering reviews associated with resolution of North service water header leaks were found to be appropriate.
Dockets Discussed:
Ter:
Operability determinations were consistent with regulatory guidance and calculations were conservative.
05000261 ROBINSON 2 09/12/1998 1998008 Pri: ENG NRC POS Pri: 4B AFW Review Sec:
Sec: 2A A review of the Auxiliary Feedwater (AFW) system determined that the system was capable of performing its safety Dockets Discussed:
function. The system engineer was knowledgeable of system status, maintenance rule data, outstanding system W
Ter:
work orders, and planned/proposed system modifications.
05000261 ROBINSON 2 09/12/1998 1998008 Pri: ENG NRC POS Prl: 4B IVSW ESR Sec:
Sec: 4A A review of an Engineering Service Request that changed the Isolation Valve Seal Water System tank operating pressure and low pressure alarm concluded that the plant change was performed in accordance with engineering Dockets Discussed:
Ter:
modification package requirements.
05000261 ROBINSON 2 Item Type (ComplianceFollowup.Other), From 09/11/1998 To 09/30/1999
Page:
11 of 17 10/0711999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 09/12/1998 1998008 Pri: ENG NRC POS Pri: 5A EDG SW Operability Determination Sec:
Sec: 4A A licensee operability determination for an Emergency Diesel Generator (EDG) Service Water piping configuration found to be different than the original design was thorough. The piping maintained structural integrity and EDG Dockets Discussed:
Ter:
operability was not affected.
05000261 ROBINSON 2 08/14/1999, 1999005 Prl: PLTSUP NRC NEG Pri: 1C Radiological Effluents Sec:
Sec:
The 1998 radiological effluents were well within release limits. The 1998 Radiological Effluent Release Report submitted to the NRC on April 29, 1999, contained numerous errors and the report will be corrected and submitted Dockets Discussed:
Ter:
with the 1999 Effluent Report.
05000261 ROBINSON 2 08/14/1999 1999005 Pri: PLTSUP NRC POS Pri: 10 Counting/Analysis Techniques.
Sec:
Sec:
The licensee maintained adequate counting room quality control charts to monitor instrumentation reliability and Dockets Discussed:
trends. The licensee routinely demonstrated the ability to accurately quantify analyses through intra-laboratory and Ter:
inter-laboratory testing and to correct analysis techniques when inaccuracies were identified.
05000261 ROBINSON 2 08/14/1999 1999005 Pri: PLTSUP NRC POS Pr: 1C Effluent Monitoring Sec:
Sec:
Effluent monitoring stations were adequately maintained and operational.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 08/14/1999 1999005 Pr: PLTSUP NRC POS Pri: 1C Radioactive Effluents and Offsite Doses Sec:
Sec:
The 1998 radiological effluents were well within release limits. The 1998 Radiological Effluent Release Report submitted to the NRC on April 29, 1999, contained numerous errors and the report will be corrected and submitted Dockets Discussed:
Ter:
with the 1999 Effluent Report.
05000261 ROBINSON 2 08/14/1999 1999005 Pri: PLTSUP NRC POS
. Pr: 1C Independent Spent Fuel Storage Installation (ISFSI)
Sec:
Sec: 5A Control of the Independent Spent Fuel Storage Installation (ISFSI) was in conformance with the commitments and requirements contained in the site-specific SFSI license and Technical Specifications. A recent audit of ISFSI Dockets Discussed:
Ter:
activities was an excellent example of the licensee's ability to perform effective program reviews and identify 05000261 ROBINSON 2 program weaknesses.
Item Type (ComplianceFollowup.Other), From 09/11/1998 To 09/30/1999
Page: 12 of17SttsD 4
C m i
io 10108/1999 10:42:32 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 08/14/1999 1999005 Prl: PLTSUP NRC POS Prl: 5C Refueling Outage 19 Radiation Exposure Planning Sec:
Sec:
The licensee was taking additional measures to minimize occupational radiation exposures for a fall refueling outage following the contamination of the reactor coolant system by leaking secondary startup sources. The licensee plans Dockets Discussed:
Ter:
to cool the containment building in order to reduce personnel contaminations and improve worker efficiency and 05000261 ROBINSON 2 safety. Licensee efforts to minimize occupational radiation exposures were good.
07/03/1999 1999004 Pri: PLTSUP NRC NEG Prl: 3A Fire Protection Equipment Use For Non-Fire Protection Functions Sec:
Sec: 1C An instance where the licensee was going to use the motor driven fire pump for non-fire protection use was Dockets Discussed:
identified. Licensee procedures related to the fire protection system provided conflicting guidance with regard to this Ter:
non-fire protection related use. The licensee plans to resolve this matter through the condition report system.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: PLTSUP NRC POS Pri: 3A Radiation Controls and Security Sec:
Sec:
Radiological controls and security practices were properly conducted. Areas observed in the radiological control Dockets Discussed:
area were appropriately posted and secured. The security plan was effectively implemented and compensatory Ter:
actions were initiated when required.
05000261 ROBINSON 2 05/22/1999 1999003 Pri: PLTSUP NRC POS Pri: 3A RCS Sampling and Analysis Sec:
Sec: 3B The sampling and analysis to determine reactor coolant system (RCS) gross activity and dose equivalent iodine-131 activity was performed by knowledgeable technicians in accordance with the licensee's procedures. Technical Dockets Discussed:
Ter:
Specification(TS) surveillance frequency requirements were being met and the RCS gross activity and dose 05000261 ROBINSON 2 equivalent iodine activity were well below TS limits.
05/22/1999 1999003-01 Pri: PLTSUP NRC NCV Pr: 3A Failure To Follow Procedure During Vehicle Search Sec:
Sec:
A violation involving the failure to follow procedures during a vehicle search was identified by the inspectors. A Dockets Discussed:
Ter:
security officer was observed filling out and signing-off a vehicle search checklist before the search was completed.
05000261 ROBINSON 2 04/10/1999 1999002 PrI: PLTSUP NRC POS Pri: iC Leaking Secondary Source Sec:
Sec:
The licensee identified the source of increased Reactor Coolant System (RCS) coolant activity as a secondary Dockets Discussed:
source leak. The total antimony activity released to the coolant was negligible with respect to Technical D
Ter:
Specification (TS) limits for gross specific activity. The licensee's action plan for dealing with the antimony was 05000261 ROBINSON 2 thorough and made good use of industry operating experience.
Item Type (Compliance.Followup.Other), From 09/11/1998 To 09/30/1999
Page:
13 of7 101999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 04/10/1999 1999002 Pri: PLTSUP NRC POS Pr: 1C Emergency Planning Drill Sec:
Sec:
An emergency drill met its objectives and provided beneficial training to the site emergency organization.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 04/10/1999 1999002 Pri: PLTSUP NRC POS Pr: 1C Fire Related Incidents Sec:
Sec:
During the period 1997 through 1999, there were four incidents of fire, smoke, or significant equipment overheating within Unit 2 safety-related plant areas. Fire related conditions were identified and mitigating actions were taken in a Dockets Discussed:
Ter:
timely manner. No significant increase or decrease in the number of fire related incidents occurred over the time 05000261 ROBINSON 2 period.
04/10/1999 1999002 Pri: PLTSUP NRC POS Pri: 1C Fire Brigade Pre-Fire Strategies Sec:
Sec:
The fire brigade pre-fire strategies were found to be satisfactory and met the requirements of the NRC approved fire protection program.
Dockets Discussed:
Ter:
05000261 ROBINSON 2 04/10/1999 1999002 Pri: PLTSUP NRC POS Prl: iC Fire Brigade Drill Program Sec:
Sec:
The fire brigade drill program and fire drill participation met the requirements of the site fire protection program. The fire brigade demonstrated good response and fire fighting performance during a simulated fire brigade drill Dockets Discussed:
Ter:
conducted during this inspection. A number of fire brigade drills had been performed in risk significant plant 05000261 ROBINSON 2 locations.
04/10/1999 1999002 Pri: PLTSUP NRC POS Pri: 1C Combustible Control Procedures Sec:
Sec: 2A The licensee's implementation of the combustible control procedures and plant operational practices In safety-related areas were consistent with the approved fire protection program. Plant housekeeping and trash Ter:
control was satisfactory. There was no adverse trend in the number of significant fire prevention program problems 05000261 ROBINSON 2 during the past two years.
04/10/1999 1999002 Pri: PLTSUP NRC POS Pri: 1C Fire Protection Program Self-Assessments Sec:
Sec: 5B The licensee's Nuclear Assessment Section assessments of the facility's fire protection program for a two-year period were effective in reporting fire protection program performance to management. The licensee's corrective Dockets Discussed:
Ter:
actions in response to previously identified issues were comprehensive and timely.
05000261 ROBINSON 2 Item Type (ComplianceFollowupOther), From 09/11/1998 To 09/30/1999
Page 1 9951731 United States Nuclear Regulatory Commission 10107/1 999 15:13:13 IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template item Title Date Source Area ID Type Codes Item Description 04/10/1999 1999002 Pri: PLTSUP NRC POS Pri: 2A Fire Brigade Equipment Sec:
Sec: 1C Personal protective fire fighting equipment provided to the brigade was in good condition, well staged, properly Dockets Discussed:
Ter:
maintained, and provided a sufficient level of personal safety needed to handle onsite fire emergencies.
05000261 ROBINSON 2 04/10/1999 1999002 Pri: PLTSUP NRC POS Pri: 2A Fire Protection Systems and Equipment Sec:
Sec: 1C Appropriate emphasis had been placed on the operability of the fire protection equipment and components. The number of degraded fire protection components was low. Manual fire fighting equipment, automatic fire detection Dockets Discussed:
Ter: 5A systems, and fire barrier features of fire zone/area walls, floors, and ceilings were operational and were well 05000261 ROBINSON 2 maintained. A National Fire Protection Association Code compliance vulnerability had been Identified by the licensee and included in the plant corrective action program. No adverse trends had been observed for fire detection system spurious alarms and Electric Thermal Link fire damper resistance values for the carbon dioxide and Halon fire suppression systems.
03/25/1999 1999010-01 Pri: PLTSUP NRC EEl Prl:
Failed To Review And Evaluate Background Information For Persons Granted Unescorted Access Sec:
Sec:
An apparent violation was identified for failure to review and evaluate background information for persons granted unescorted access authorization in accordance with 10 CFR 73.56 (b)(3) and the licensee's plans and procedures Dockets Discussed:
Ter:
and the failure to maintain complete and accurate records of these reviews in accordance with 10 CFR 50.9.
05000261 ROBINSON 2 03/25/1999 1999010-02 Pri: PLTSUP NRC EEl Pri:
Continuation Of The Granting Unescorted Access Sec:
Sec:
An apparent violation was Identified for the failure to discontinue temporary unescorted access authorization for Dockets Discussed:
Te three individuals having inaccurate background information records as required by 10 CFR 73.56(b) and licensee's
- e Ter:
plans and procedures.
05000261 ROBINSON 2 03/25/1999 1999010-03 Pr: PLTSUP NRC EEl Pr:
Failure To Maintain Access Authorization Original Data Sec:
Sec:
An apparent violation was identified for failure to maintain original data upon which the licensee granted unescorted Dockets Discussed:
Ter:
access authorization for five years as required by 10 CFR 73.56 (h)(1).
05000261 ROBINSON 2 03/25/1999 1999010-04 Pri: PLTSUP NRC EEl Prl:
Failure To Log Safeguards Events Within 24 Hours Of Discovery.
Sec:
Sec:
An apparent violation was identified for the failure to log safeguards events in the security event logs in accordance Dockets Discussed:
Ter:
with 10 CFR 73.71 (c).
05000261 ROBINSON 2 Item Type (Compliance.Followup Other), From 09/11/1998 To 09/30/1999
Page: 15of17 N cerC m iso 10/07/1999 1513:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Region II ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 03/25/1999 1999010-05 Pri: PLTSUP NRC EEl Pri:
Failure To Document Individuals Training In Accordance With Licensee Requirements.
Sec:
Sec:
An apparent violation was identified for the failure to document training in accordance with the licensee's plans and Dockets Discussed:
Ter:
procedures.
05000261 ROBINSON 2 02/27/1999.
1999001 Pri: PLTSUP NRC NEG Pri: 3A Human Error During Resin Transfer Sec:
Sec:
Human error during a resin sluice caused displacement of resin into the auxiliary building drains and sump. The cleanup and resin recovery efforts resulted in personnel doses of approximately 325 millirem. All contaminated floor Dockets Discussed:
Ter:
space was promptly decontaminated.
05000261 ROBINSON 2 02/27/1999 1999001 Pri: PLTSUP NRC POS Pri: 3A Plant Support Radiological Controls and Security Sec:
Sec:
Radiological controls and security practices were properly conducted. Areas observed in the radiological control area were appropriately posted and secured. The security plan was effectively implemented and compensatory Dockets Discussed:
Ter:
actions were initiated when required.
05000261 ROBINSON 2 12/11/1998 1998013 Pri: PLTSUP NRC POS Pri: IC Safeguards event Sec:
Sec: 5A The inspector verified that the licensee, based on initial information, had reported a safeguards event to the NRC within one hour. Based on subsequent investigations, the licensee concluded that the event was not to be reported Dockets Discussed:
Ter: 5B to the NRC within one hour and withdrew the report. The licensee logged the event in the 24-hour security event 05000261 ROBINSON 2 log. The inspector concluded that the licensee was correct in withdrawing the one-hour report.
12/11/1998 1998013 Pri: PLTSUP NRC POS Prl: 2A New Security Computer Installation Sec:
Sec: 1C The licensee had installed a new state-of-the-art "MEECA" computer on July 10, 1998. The inspector observed the alarm station during operation on December 10, 1998, and concluded that the new computer operationally exceeded Dockets Discussed:
Ter:
the capability of the previous computer and that the newly installed "MEECA" computer capability met the NRC 05000261 ROBINSON 2 requirements. Also, positive controls were in place to ensure that ony authorized personnel were granted access to the plant.
12/11/1998 1998013 Pri: PLTSUP NRC POS Pri: 2A Security Facilities and Equipment Sec:
Sec: 4B The licensee's security facilities and equipment were determined to be well maintained and reliable. The excellent engineering and instrumentation and control personnel support were the major contributing factor to continued Dockets Discussed:
Ter: 2B operability of the detection and assessment equipment.
05000261 ROBINSON 2 Item Type (Compliance, Followup, Other), From 09/11/1998 To 09/30/1999
Page:
16 of 17 110/11999 5:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE-MATRIX By Primary Functional Area Region it ROBINSON Functional Template Item Title Date Source Area ID Type Codes Item Description 12/11/1998 1998013 Pri: PLTSUP NRC POS Prl: 3B Security Force Capability Sec:
Sec:
The security force members adequately demonstrated that they had the requisite knowledge necessary to effectively implement the duties and responsibilities associated with their contingency response positions. The licensee's Dockets Discussed:
Ter:
actions to implement NRC Information Notice (IN) 98-35, "Threat Assessments and Consideration of Heightened 05000261 ROBINSON 2 Physical Protection Measures," dated September 4, 1998, were reviewed and considered adequate.
10/24/1998 1998009 Pri: PLTSUP NRC POS Pri: IC Emergency Preparedness Program Sec:
Sec:
The licensee's emergency program was being maintained in a state of full operational readiness. Changes to the program since the last inspection were consistent with commitments and NRC requirements, and did not decrease Dockets Discussed:
Ter:
the licensee's overall state of preparedness.
05000261 ROBINSON 2 10/24/1998 1998009 Pri: PLTSUP NRC POS Pri: 3A Radiation Control and Security Sec:
Sec:
Radiation control and security practices were properly conducted. Inspected areas in the Radiation Control Area (RCA) were noted to be appropriately posted and secured as necessary. The security plan was effectively Dockets Discussed:
Ter:
implemented and compensatory actions were initiated when required.
05000261 ROBINSON 2 09/12/1998 1998008 Pri: PLTSUP NRC POS Prl: 3A CVCS Filter Replacement Sec:
Sec: IC Radiological controls utilized during a Chemical and Volume Control System filter replacement were effective in Dockets Discussed:
Ter:
minimizing personnel exposure and contamination.
05000261 ROBINSON 2 Item Type (Compliance Followup Other), From 09/11/1998 To 09/30/1999
Page: 17 of 17 10/07/1999 15:13:13 United States Nuclear Regulatory Commission IR Report 3 PLANT ISSUE MATRIX By Primary Functional Area Legend Type Codes:
Template Codes:
Functional Areas:
BU Bulletin 1A Normal Operations OPS Operations CDR Construction 1 B Operations During Transients MAINT Maintenance DEV Deviation 1C Programs and Processes ENG Engineering EEl Escalated Enforcement Item 2A Equipment Condition PLTSUP Plant Support IFI Inspector follow-up item 2B Programs and Processes OTHER Other LER Licensee Event Report 3A Work Performance LIC Licensing Issue 3B KSA MISC Miscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 4B Engineering Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion 5A Identification NON Notice of Non-Conformance 5B Analysis OTHR Other 5C Resolution P21 Part 21 POS Positive SGI Safeguard Event Report STR Strength ID Codes:
URI Unresolved item NRC NRC VIO Violation Self Self-Revealed WK Weakness Licensee Licensee EEls are apparent violations of NRC Requirements that are being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the EEls and the PIM entries may be modified when the final decisions are made.
URIs are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation. A URI may also be a potential violation that is not likely to be considered for escalated enforcement action. However, the NRC has not reached its final conclusions on the issues, and the PfM entries may be modified when the final conclusions are made.
Item Type (ComplianceFollowup.Other), From 09/11/1998 To 09/30/1999
ROBINSON INSPECTION PLAN INSPECTION NUMBER OF PLANNED PROCEDUREl TITLE/PROGRAM AREA INSPECTORS INSPECTION DATES TYPE OF INSPECTION TEMPORARY COMMENTS INSTRUCTION IP 73753 Maintenance 1
10/99 Core Inspection (Outage 151)
IP 83750 Radiation Protection 1
10/99 Core Inspection IP 84750/86750 Radiation Protection 1
11/99 Core Inspection IP 82301 EP Exercise 3
12/99 Core Inspection IP 40500 Corrective Action 4
2/00 Core Inspection