ML14314A754
| ML14314A754 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/23/1999 |
| From: | Brian Bonser NRC/RGN-II, NRC/IE |
| To: | Young D Carolina Power & Light Co |
| References | |
| NUDOCS 9904020157 | |
| Download: ML14314A754 (31) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9904020157 DOC.DATE:.99/03/23 NOTARIZED: NO DOCKET #
FACIL:50-261 H.B. Robinson Plant, Unit 2, Carolina Power & Light C 05000261 AUTH.NAME AUTHOR AFFILIATION BONSER,B.R..
Region 2 (Post 820201)
RECIP.NAME RECIPIENT AFFILIATION YOUNG,D.E.
Carolina Power & Light Co.
SUBJECT:
Advises of planned insp effort resulting from plant PPR review completed on 990204.Historical listing of plant issues & details of insp plan for next eight months encl.
A DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR I ENCL I SIZE: 30 TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
E RECIPIENT COPIES RECIPIENT COPIES G
ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL O
PD2-1 PD 1
1 SUBBARATNAM 1
1 R
INTERNAL: AEOD/SPD/RAB 1
1 AEOD/TTC 1
1 DEDRO 1
1 FILE CENTER>
1 1
NRR/DRCH/HOHB 1
1
'NRR/DRPM/PECB 1
1 NRR/DRPM/PERB 1-1 NUDOCS-ABSTRACT 1
1 OE DIR 1
1 OGC/HDS3 1
1 2
RGN2 FILE 01 1
1 EXTERNAL: LMITCO MARSHALL 1
1 NOAC 1
1 NRC PDR 1
1 NUDOCS FULLTEXT 1
1 0
C U
M E
N T
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.
TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17
March 23, 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:
PLANT PERFORMANCE REVIEW - H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2
Dear Mr. Young:
On February 4, 1999, the NRC staff completed a Plant Performance Review (PPR) of H. B.
Robinson Steam Electric Plant Unit 2. The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance. The results are used by NRC management to facilitate planning and allocation of inspection resources. PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC's senior management meeting (SMM) reviews. PPRs examine information since the last assessment of licensee performance to evaluate long term trends, but emphasize the last six months to ensure that the assessments reflect current performance.
The PPR for Robinson involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period February 1997 through January 1999. The NRC's most recent summary of licensee performance was provided in a letter of March 11, 1997, and was discussed in a public meeting with you on March 25, 1997.
As discussed in the NRC's Administrative Letter 98-07 of October 2, 1998, the PPR provides an assessment of licensee performance during an interim period that the NRC has suspended its Systematic Assessment of Licensee Performance (SALP) program. The NRC suspended its SALP program to complete a review of its processes for assessing performance at nuclear power plants. At the end of the review period, the NRC will decide whether to resume the SALP program or terminate it in favor of an improved process.
During the last six months the unit operated at or near full power except for one reactor trip and one forced outage. An automatic trip occurred on October 17, 1998, due to the failure of a nuclear instrumentation power supply and condenser steam dump valve. There was also a unit shutdown on January 8, 1999, to repair a containment isolation valve.
Overall performance at Robinson was acceptable and the plant continued to be operated in a safe manner. Nuclear safety continued to be emphasized by plant management and was an integral part of the decision-making process. The corrective action and self-assessment programs continued to be a strength. In general, maintenance activities remained consistent during the evaluation period. Engineering continued to provide effective support to the plant.
Performance in the operations area was consistent. Normal plant operation activities, shutdown/startup evolutions, and response to plant transients were generally appropriate and conservative. Management attention was placed on human error reduction to address previous performance issues and some improvement has been noted. System configuration was well controlled and plant housekeeping was considered excellent. Operator workarounds and nuisance alarms were kept at low levels and received sufficient management attention. Plant 9904020157 990323 OFFICIAL COPY PDR ADOCK 05000261 0
CP&L 2
Nuclear Safety Committee, Nuclear Assessment, and self assessment activities continued to be a strength. The Condition Report system was effectively utilized to document, track, and trend problems, and effectively managed the corrective action program. The requalification program remains effective. An initial operator license examination met NRC guidelines and overall candidate performance was satisfactory. The core inspection program and initial operator examinations are planned in the operations area.
Maintenance activities remained consistent during the evaluation period. Human performance problems were identified in instrument calibration activities as indicated by mispositioning of potentiometers which caused steam dump and feedwater regulating valve failures. Plant material condition and equipment performance were consistent. Inservice inspection activities were conducted in accordance with approved procedures and technical requirements. Post maintenance and operability testing was conducted satisfactorily. In addition to the core inspections, an initiative inspection is planned to review instrument surveillance testing and calibration due to the identified human performance problems.
Performance in the engineering area was consistent. Support for plant operations was usually effective. Evaluations and operability determinations were thorough and system engineers provided good support to maintaining operability of their assigned systems. The design control process for inspection of the containment liner was well controlled. Engineering failed to ensure that the maintenance program provided for replacement of Agastat relays at the end of their service life. Problem identification, analysis, and resolution was consistent. The core inspections in the engineering area are planned.
The radiation protection program was consistent and effective in implementing regulatory requirements. Overall the As Low As Reasonably Achievable (ALARA) program continued to be effective. The control, packaging, and transportation of solid radioactive waste met applicable regulatory requirements. The liquid and gaseous radioactive waste streams were adequately maintained and no adverse trends in radiological effluents were identified. The Independent Spent Fuel Storage Facility was adequately maintained. The emergency preparedness program continued to maintain the site in a state of full operational readiness to respond to emergencies. The performance of the program showed a consistent trend. Security continued to perform in a consistent manner. Security personnel demonstrated that they were fully capable of performing their duties on a day-to-day basis. Additionally, security personnel were highly trained and equipped to respond to contingency events as demonstrated during force-on-force drills. Security equipment was well maintained which resulted in reduced compensatory hours. The core inspections are planned in the plant support area. 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 view of licensee performance trends. The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and Robinson. 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.
This letter advises you of our planned inspection effort resulting from the Robinson PPR review.
It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Enclosure 2 details our inspection plan for the next eight months. The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for
CP&L 3
emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.
We will inform you of any changes to the inspection plan. If you have any questions, please contact me at 404-562-4560.
Sincerely, Orig signed by Brian 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 4)
CP&L 4
cc w/encls:
J. W. Moyer William D. Johnson Director, Site Operations Vice President & Senior Counsel Carolina Power & Light Company Carolina Power & Light Company H. B. Robinson Steam Electric Plant P. 0. Box 1551 3581 West Entrance Road Raleigh, NC 27602 Hartsville, SC 29550 Karen E. Long T. Walt, Plant General Manager Assistant Attorney General Carolina Power & Light Company State of North Carolina H. B. Robinson Steam Electric Plant P. 0. Box 629 3581 West Entrance Road Raleigh, NC 27602 Hartsville, SC 29550 Robert P. Gruber T. C. Morton, Manager Executive Director Performance Evaluation and Public Staff - NCUC Regulatory Affairs CPB 9 P. 0. Box 29520 Carolina Power & Light Company Raleigh, NC 27626-0520 P. 0. Box 1551 Raleigh, NC 27602-1551 Public Service Commission State of South Carolina H. K. Chernoff, Supervisor P. 0. Box 11649 Licensing/Regulatory Programs Columbia, SC 29211 Carolina Power & Light Company H. B. Robinson Steam Electric Plant Hartsville Memorial Library 3581 West Entrance Road 147 W. College Avenue Hartsville, SC 29550 Hartsville, SC 29550 T. M. Wilkerson, Manager Distribution w/encls: (See page 5)
Regulatory Affairs Carolina Power & Light Company H. B. Robinson Steam Electric Plant 3581 W. Entrance Road Hartsville, SC 29550 Virgil R. Autry, Director Div. of Radioactive Waste Mgmt.
Dept. of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Mel Fry, Director Division of Radiation Protection N. C. Department of Environment, Health and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721
CP&L 5
Distribution w/encls:
S. Collins, NRR J. Zwolinski, NRR W. Dean, NRR T. Boyce, NRR C. Thomas, NRR R. Subbaratnam, NRR G. Tracy, EDO J. Lieberman, OE B. Bonser, Rll PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 2112 West Old Camden Road Hartsville, SC 29550 OFFICE DPRIRII DRS/RII DRS"I DRSI I DRS/Ri_
SIGNATURE j3 NAME GMacDonald:vg tBar A&ell HCnristensen KLandid.
DATE
.3//f 199 "3/a 199
/z2/99 o31 99 3/
199
-3/
199 cOPY?
ES NO NO
/YES /
NO S
NO ES/
NO YES NO YES NO OFFIlAL RECORD COPY DOCU T NAME: G:1R ON\\PPRIPPR.LTK
Page: 1 of 5 Date: 03/23/1999 United States Nuclear Regulatory Commission Time: 13:40:01 Region II PLANT ISSUE MATRIX ROBINSON By Primary Functional Area Functional Template Date Source Area ID Type Codes Item Description 01/16/1999 1998012 Pri: OPS Licensee MISC Pri: IC The licensee aproached the Ultimate Heat Sink temperature limit during the Summer of 1998. A Notice of Sec:
Sec: 5A Enforcement Discretion (NOED) and an exigent Technical Specification (TS) amendment were granted to extend the TS action time. The licensee never exceeded the temperature limit and did not use the extra Ter action statement time allowed by the NOED and the TS amendment.
01/16/1999 1998012 Pri: OPS Licensee NEG Pri: 3A A human error in not using existing procedural guidance to perform a valve line-up on a non-safety related Sec:
Sec:
system resulted in water intrusion into the "A" Emergency Diesel Generator (EDG) room. EDG operability was not affected.
Ter:
01/16/1999 1998012 Pri: OPS NRC POS Pri: IA Operations perfomance during shutdown and startup activities for a maintenance outage was well planned Sec:
Sec:
and executed.
Ter:
01/16/1999 1998012 PrI: OPS NRC POS Pri: IC A review of licensee overtime during refueling outage 18 concluded that the licensee was meeting See:
Sec:
requirements.
Ter:
01/16/1999 1998012 Pri: OPS NRC POS Pri: IC The recent transition to electronic logkeeping was well planned and operators were given sufficient training Sec:
Sec:
before implementation.
Ter:
12/05/1998 1998011 Pri: OPS NRC POS PI: 1A A detailed system walkdown found that the-Safety Injection System was appropriately configured to perform Sec:
Sec: 2A its design function.
Ter.
12/05/1998 1998011 Pri: OPS NRC POS Pri: IC The onsite review functions of the Plant Nuclear Safety Comittee (PNSC) were conducted in accordance Sec:
Sec:
with Technical Specifications. During the PNSC meetings topics were thoroughly discussed and evaluated.
Ter 12/05/1998 1998011 Pri: OPS NRC POS Pri: IC The licensee program for cold weather protection was adequately implemented. Freeze protection panels Sec:
Sec: 2A and circuits, as well as, temporary enclosures and heaters were appropriately installed and maintained per procedure.
Ter 2B 12/05/1998 1998011 Pri: OPS NRC POS Pri: IC A clearance associated with a charging pump was correctly implemented. A review of existing clearances Sec: MAINT Sec:
identified that clearances older than three months had been evaluated in accordance with licensee procedures and did not impact plant safety.
Ter:
- Enclosure 1 Item Type (ComplianceFollowupOther), From 10/01/1997 To 06/17/2000
Page:
2 of 5 Date: 03/23/1999 United States Nuclear Regulatory Commission Time: 13:40:01 Region II PLANT ISSUE MATRIX ROBINSON By Primary Functional Area Functional Template Date Source Area ID Type Codes Item Description 10/24/1998 1998009 Pri: OPS NRC NEG Pri: 3A Two examples of operator inattention to detail were identified involving operators not recognizing a failed Sec:
Sec:
Emergency Response Facility Information System printer and the subsequent missed review of plant parameters; and documentation completeness during an emergency diesel generator surveillance.
Ter:
10/24/1998 1998009 Pri: OPS NRC POS Pri: I B Operator response to a turbine trip and automatic reactor trip was appropriate and in accordance with Sec:
Sec: 5B procedures. The licensee's event review was thorough and the findings identified the root causes of the event. The licensee appropriately generated Condition Reports to track planned corrective actions.
Ter:
10/24/1998 1998009 Pri: OPS NRC POS Pri: IC Simulator examinations observed demonstrated the effectiveness of licensed operator requalification Sec:
Sec:
training. Simulator examination scenario guides were well developed and detailed. Operator performance was effectively assessed by the training department.
Ter:
10/24/1998 1998009 Pri: OPS NRC POS Pri: IC A Maintenance and Test Equipment (M&TE) program review concluded that the program met the Sec: MAINT Sec:
requirements of the Updated Final Safety Analysis Report (UFSAR) and was implemented in accordance with procedural requirements. Out-of-tolerance M&TE was identified and applicable procedure steps were Ter:
reperformed with appropriately calibrated test equipment. The M&TE calibration laboratory personnel were knowledgeable of program requirements. M&TE calibration history, calibration requirements and frequency and the basis for the program were well maintained.
09/12/1998 1998008 Pri: OPS Licensee NEG Pri: 2A Two components were found to be out of their normal position. Appropriate corrective actions were taken Sec:
Sec: 5A to restore these components to their normal configuration. The safety significance for both these events was minimal.
Ter:
09/12/1998 1998008 Pri: OPS NRC POS Pri: IA The licensee took appropriate measures to prepare the site for adverse weather conditions in anticipation of Sec: PLTSUP Sec:
Hurricane Bonnie.
Ter:
08/02/1998 1998008-01 Pri: OPS Licensee NCV Pri: 3B A Non-cited violation (NCV) was identified involving a failure to perform Technical specification (TS) required Sec:
Sec:
iodine sampling following a power reduction. Operators did not fully understand the requirements for sampling dose equivalent iodine following a rapid power change.
Ter:
01/16/1999 1998012 Pri: MAINT NRC POS Pri: 3A Licensee actions to repair a weld leak in the Chemical and Volume Control System were well managed and Sec:
Sec:
coordinated between Operations, Engineering and Maintenance. Operability determinations were thorough and conservative. Repairs were performed in accordance with procedures. One concern was Ter identified with regard to the staging of a wooden plug required for loss of freeze seal contingency plans.
12/05/1998 1998011 Pri: MAINT NRC POS Pri: 5A Licensee response and actions with regard to a Reactor Coolant System (RCS) flow transmitter tubing fitting Sec:
Sec: 5B leak were conservative and technically sound. Compensatory measures were instituted to monitor the leak until a shutdown repair can be made. There were no operability concerns identified and the RCS leak was Ter: 2A within TS leak rate Imits.
Item Type (Compliance,FollowupOther), From 10/01/1997 To 06/17/2000
Page: 3 of5 U ie StesDate:
03/23/1999 United States Nuclear Regulatory Commission Time: 13:40:01 Region II PLANT ISSUE MATRIX ROBINSON By Primary Functional Area Functional Template Date Source Area ID Type Codes Item Description 12/05/1998 1998011 Pri: MAINT NRC POS Pri: 3A During an EDG fuel oil system flow test, the reactor operator performing the test exhibited a good Sec: OPS Sec: 2B questioning attitude by identifying a procedural step that would have rendered both EDGs inoperable. The procedural deficiency was not recognized by procedure writers and reviewers or by operators during a Ter 3B pre-surveillance briefing.
10/24/1998 1998009-01 Pri: MAINT Licensee NCV Pri: 2B A Non-Cited Violation was identified Involving two inadequate Technical Specification required surveillance Sec:
Sec:
procedures Involving valve position verification. The affected valves were verified to be in their required position. Licensee corrective actions were appropriate.
Ter:
09/12/1998 1998008 Pri: MAINT Licensee NEG Pri: 3A 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 See:
See:
retesting of valve CC-749A could have been performed In a more timely manner.
Ter:
01/16/1999 1998012 Pri: ENG NRC POS Pri: 4A A temporary modification to jumper a portion of the "A" reactor coolant pump oil reservoir level limit switch See:
Sec:
was comprehensive and In accordance with procedures. The temporary modification provided the compensatory action for the degraded condition and restored the associated control room annunciator.
Ter:
12/05/1998 1998011-03 Pri: ENG NRC NEG Pri: 2A The Inspectors noted inconsistencies with the actual dedicated shutdown diesel generator governor speed Sec:
See:
droop setting and the setting described in the system description and vendor manual. The safety significance was minimal as an operator is stationed at the diesel control panel during station blackout to Ter:
control frequency. The system engineer appropriately initiated a condition report to revise procedures to reflect vendor recommendations.
10/24/1998 1998009 Pri: ENG NRC POS Pri: 4B Engineering reviews associated with resolution of north service water header leaks were found to be Sec:
Sec:
appropriate. Operability determinations were consistent with regulatory guidance and calculations were conservative.
Ter:
10/24/1998 1998009-02 Pri: ENG NRC URI Pri: 2B The Inspectors identified the lack of a preventive maintenance progam which would identify Agastat series See:
Sec:
E7000 relays which exceeded their service life.
Ter:
09/12/1998 1998008 Pri: ENG NRC POS Pri: 4B A review of the Auxiliary Feedwater (AFW) system determined that the system was capable of performing its Sec:
Sec: 2A safety function. The system engineer was knowledgeable of system status, maintenance rule data, outstanding system work orders, and planned/proposed system modifications.
Ter:
09/12/1998 1998008 Pri: ENG NRC POS Pri: 48 A review of an Engineering Service Request that changed the Isolation Valve Seal Water System tank Sec:
Sec: 4A operating pressure and low pressure alarm concluded that the plant change was performed in accordance with engineering modification package requirements.
Ter:
Item Type (Compliance,FollowupOther), From 10/01/1997 To 06/17/2000
Page: 4 of5 UntdDate:
03/23/1999 United States Nuclear Regulatory Commission Time: 13:40:01 Region II PLANT ISSUE MATRIX ROBINSON By Primary Functional Area Functional Template Date Source Area ID Type Codes Item Description 09/12/1998 1998008 Pri: ENG NRC POS Pri: 5A A licensee operability determination for an Emergency Diesel Generator (EDG) Service Water piping Sec:
Sec: 4A configuration found to be different than the original design was thorough. The piping maintained structural integrity and EDG operability was not affected.
Ter:
10/24/1998 1998009 Pri: PLTSUP NRC POS Pri: IC The licensee's emergency program was being maintained in a state of full operational readiness. Changes Sec:
Sec:
to the program since the last inspection were consistent with commitments and NRC requirements, and did not decrease the licensee's overall state of preparedness.
Ter 10/24/1998 1998009 Pri: PLTSUP NRC P0S Pri: 3A Radiation control and security practices were properly conducted. Inspected areas in the Radiation Control Sec:
Sec:
Area (RCA) were noted to be appropriately posted and secured as necessary. The security plan was effectively Implemented and compensatory actions were initiated when required.
Ter 09/12/1998 1998008 Pri: PLTSUP NRC POS Pri: 3A Radiological controls utilized during a Chemical and Volume Control System filter replacement were Sec:
Sec: 1C effective in minimizing personnel exposure and contamination.
Ter Item Type (Compliance,Followup,dOther), From 16/01/1997 To 06/17/2000
Page: 5 of 5 Date: 03/23/1999 United States Nuclear Regulatory Commission Time: 13:40:01 PLANT ISSUE MATRIX By Primary Functional Area Legend Type Codes:
Template Codes:
Functional Areas:
BU Bulletin I A Normal Operations OPS Operations CDR Construction I B Operations During Transients MAINT Maintenance DEV Deviation 1 C Programs and Processes ENG Engineering EEI Escalated Enforcement Item 2A Equipment Condition PLTSUP Plant Support IFl 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 P21 Part 21 5C Resolution POS Positive ID Codes:
SGI Safeguard Event Report NRC NRC STR Strength Self Self-Revealed URI Unresolved item Licensee Licensee VIO Violation WK Weakness 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.
UPIs 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 PIM entries may be modified when the final conclusions are made.
Item Type (ComplianceFollowup,Other), From 10/01/1997 To 06/17/2000
United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES bPERATIO6NS 9/3/1998 Negative IR 98-07 NRC Events associated with the June 29, 1998 EDG testing exhibited an instance of non 1 2 3 4 5
conservative decision making. Licensee followup of the event was thorough and safety consequences were minimal.
AOO 0 00 CO 0OO 9/3/1998 Negative IR 98-07 NRC Operators took appropriate actions in responding to a power transient resulting from 1 2 3 4 5 a control failure of the low pressure heater bypass valve. The inspector noted that the operator exhibited inattention to detail and unfamiliarity with system component A
O OO 0 0 in incorrectly determining bypass valve position.
B 00000 C 0 000 8/20/1998 Positive IR-98-07 NRC The inspectors concluded that the Corrective Action Management program was 1 2 3 4 5 effectively implemented. The licensee demonstrated effective controls for the identification, resolution, and prevention of issues that would degrade the quality of A O 0 0 0 0 plant operations and safety. Corrective actions were generally thorough, although two examples were identified where the corrective actoins were not totally effective.
B O OO 0 0 Defect repetitiveness, system and component operability, and industry events, when C 11 0 0 0 required, were addressed in each of the CRs reviewed.
8/20/1998 Strength ENG IR-98-07 NRC Training feedback and evaluation programs were effectively implemented.
1 2 3 4 5 Procedure requirements were met and the timeliness of corrective actions were satisfactory. The licensee's use of operating experience was a strength.
A OOODE B 00000 CO 000 8/20/1998 Strength ENG IR-98-07 NRC The Nuclear Assessment Section and Self-Assessments were a program strength.
1 2 3 4 5
This was based upon the number, level of detail, quality of the assessments, and the significance of the findings. Corrective actions implemented for the identified items A OO O 0 0 were generally satisfactory. Management demonstrated a proactive attitude with respect to self-assessments and corrective actions.
B O O 0 0 CO 000 8/20/1998 Weakness ENG IR-98-07 NRC The quality and detail of 10 CFR 50.59 safety evaluations was a weakness. Some 1 2 3 4 5
screening question answers were not thorough and detailed and were not of sufficient detail to ensure an independent reviewer could draw the same conclusion A OO 0 0 O and arrive at the same answer. The inspectors observed some improvement in the quality and detail of two recently completed 10 CFR 50.59 safety evaluations.
B OO 1 1 0 0 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 1 of 19 FOR PUBLIC RELEASE Last Updated 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 8/20/1998 Positive IR-98-07 NRC Problem identification and resolution were effectively implemented. Plant problems 1 2 3 4 5
were appropriately assessed for potential significance, work request were correctly assigned a priority, and deficient items were appropriately entered into the corrective A 0DOO 0 0 action program. Probabilistic Safety Assessments were effectively used in work control management.
BOOOOO CO 000 7/27/1998 NCV IR 98-06 LICENSEE A Non-Cited Violation (NCV) related to failure to appropriately log the Motor Driven 1 2 3 4 5
Auxiliary Feedwater (MDAFW) pump inoperable and enter the appropriate Technical Specification (TS) action statement was identified (Section 02.1).
A 0 0 0 0 0 BOOO CO 000 6/29/1998 VIO IR98-05 LICENSEE A violation for failure to perform a required surveillance test on the containment 1 2 3 4 5
personnel air lock test was identified (Section 04.1).
A 00000 CO 000 6/29/1998 Negative IR98-05 NRC Reactor operator response to the failed closed turbine control valve was incorrect.
1 2 3 4. 5 Licensee plans to review this event to enhance future training activities. Overall plant response was appropriate. Reactor startup activities following the trip were A 0 0 0 0 0 uneventful (Section 02.1).
B 000 0 0 B 00000 CO 000 6/29/1998 Positive IR98-05 NRC The inspector observed portions of startup related activities and concluded that 1 2 3 4 5
management decision to suspend startup to verify potential affects of the seismic event were conservative. The inspector did not note any affect to the plant as a A 0 0 0 0 0 result of the seismic event. Operator performance during startup was considered good (Section 01.3).
B 0000 0 CO 000 6/29/1998 NCV IR 98-05 SELF A non-cited violation involving inadequate testing of refueling equipment was 1 2 3 4 5 identified. There were no direct safety consequences of the fuel assembly drop incident. Had an irradiated assembly been subject to a similar drop, any release of A 0 0 0 0 0 radioactivity would have been contained, due to containment closure requirements during fuel movement. Licensee follow up to this event was appropriate (Section B 0 0 0 0 0 01.2).
C 0 000 4/27/1998 Positive IR 98-02 NRC Nuclear Assessment Section and Plant Nuclear Safety Committee continued to 1 2 3 4 5 provide strong oversight, including during refueling outage 18 (Section 07.1).
A 00000 B 00000 c 0 000 FROM: 10/1/1997 TO: 3/23/1999 Page 2 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/1998 Negative IR 98-02 SELF The Reactor Coolant System draindown and overflow of approximately 200 gallons 1 2 3 4 5
of water onto the containment floor exhibited a weakness on part of operations in the monitoring of available indications. The normal level of attention to detail was not A D 0 0 0 O exhibited by operations that contributed to this event (Section 01.4).
B 00000 CO 000 4/27/1998 NCV IR 98-02 LICENSEE A non-cited violation for not having both residual heat removal trains operable in 1 2 3 4 5
Mode 6 was identified by the licensee (Section 01.3).
A 00000O a00000.
c E 0 0
100 4/27/1998 Negative IR 98-02 NRC An issue related to logging of Technical Specification action statement identified by 1 2 3 4 5
the inspector was promptly corrected (Section 01.1).
B 00000 CO 000 4/13/1998 Strength IR 98-300 NRC The examiners identifed generic strengths in the following areas: communications 1 2 3 4 5
and the use of plant announcements. (Section 05.3)
A 00000 B 00000 CO 000 4/13/1998 Weakness IR 98-300 NRC The examiners identifed operating test generic performance weaknesses in the 1 2 3 4 5
following areas: Subcooling Margin calculation, the use of plant curves to determine Emergency Diesel Generator Loading, and the prediction of plant response during A 0 O 0 O 0 nuclear instrument testing. (Section 05.3)
B k20000@
CO 000 4/13/1998 Weakness IR 98-300 NRC The examiners identified potential generic knowledge weaknesses, based on written 1 2 3 4 5
examination evaluation, in the following areas: Technical Specification design of Spent Fuel Pool Reactivity, operator actions for seal failures, trip logic for S/G low A OO 0 0 0 level, adjustment of Power Range Nuclear Instruments during testing, reactivity control during reactor start up with both Source Range Nuclear Instruments failing, B 0 0 0 0 0 prediction of plant parameters following a Reactor Coolant Pump trip, effects of a safety valve failing open, basis for tripping the turbine following an ATWS, actions and basis for rod insertion limits following a turbine runback and boric acid addition following two stuck rods. (Section 05.3)
FROM: 10/1/1997 TO: 3/23/1999 Page 3 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/13/1998 Negative IR 98-300 NRC The submitted written examination was acceptable with the exception of a limited 1 2 3 4 5
number of written question distractors which lacked plausibility. The submitted operating examinations were acceptable, however, five prescripted JPM questoins A 0 0 0 0 0 contained incomplete answers, resulting in licensee generated post-examination comments. (Section 05.2)
B O 0
0 C 0 000 4/13/1998 Positive IR 98-300 NRC Control room activities were observed during the examination validation week and 1 2 3 4 5
examination administration week. The operators were found to be attentive and professional in their duties. (Section0l.1)
A 1 0 0 0 0
B 10 0 0 CO 000 2/2/1998 Negative IR 97-14 SELF The licensee promptly and adequately implemented and planned corrective actions 1 2 3 4 5
to retum the "A" Emergency Diesel Generator to operable status following inadvertent wetting of equipment due to inappropriate valve lineup on the service A 0 0 0 0 0 water system (Section 02.1).
B 00000 CO 000 2/2/1998 Negative IR 97-14 NRC The inspector identified that the licensee had erroneously included the wrong heatup 1 2 3 4 5
and cooldown limit curves during the implementation of improved TS. The licensee determined that these errors were caused by inattention to detail. The potential AOO 0 OO safety implications were minimal due to plant procedures specifically prescribing the correct heatup and cooldown limits (Section 01.2).
B 0OOO CO 000 12/22/1997 Negative IR 97-12 NRC The failure to properly implement Regulatory Guide commitments as descibed in the 1 2 3 4 5
Updated Final Safety Analysis Report (UFSAR) associated with the Loose Parts Monitoring Program was considered similar to deficiencies and inconsistencies in A 0 0 0 0 0 the UFSAR and other licensing documents previously identified during the NRC's Architectural Engineering (A/E) Team Inspection. 4B B OO0 0 0 CO 000 12/22/1997 Positive IR 97-12 NRC The onsite review functions of the Plant Nuclear Safety Committee (PNSC) were 1 2 3 4 5
conducted in accordance with TS. The PNSC meetings were well coordinated and meeting topics were thoroughly discussed and evaluated. NAS continued to provide A OO 0 0
strong oversight of licensee activities. A NAS assessment of the Robinson Moter Operated Valve program was thorough and resulted in important findings. 1C B 0 O 0 0 0 CO 000 12/22/1997 Positive IR 97-12 NRC The licensee's implementation and transition to the Improved Technical 1 2 3 4 5
Specifications was good. 1C A 00000 B 0O000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 4 of 19 FOR PULlIC REILEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/22/1997 Positive IR 97-12 NRC Overall, licensee implementation of cold weather protection activities was 1 2 3 4 5
satisfactory and the system engineer was familiar with plant cold weather protection equipment. Additionally, a Nuclear Assesment Section (NAS) audit of the plant cold A O 0 0 0 weather protection activities was thorough, and condition reports were appropriately initiated to address several dificiencies that were identified by the NAS audit. 1 A B 0 0 0 0 0 c 0 000 12/22/1997 NCV IR 97-12 NRC Two Non-Cited Violations (NCVs) were identified involving operator failure to follow 1 2 3 4 5
procedures while implementing Technical Specification (TS) surveillance requirements. While individually, each of these items had low safety consequence, A 0 0 0 0 0 they indicated weaknesses in operator log keeping accuracy and operator attention to detail. 1A/3A B OOOOO0 CO 000 12/22/1997 Positive IR 97-12 NRC Overall, operator response to the failure of a condensate pump shaft and 1 2 3 4 5 subsequent automatic reactor trip was appropriate. Plant shutdown and startup activities were satisfactorily conducted. Ineffective corrective actions from a similar A
0 0 0 0 0 condensate pump shaft failure that occurred in 1991 resulted in the subsequent failure on November 16, 1997. 1B/5C B 00000 CO 000 12/7/1997 Positive MAINT IR 97-11 NRC The overall approach to assessing the risk-impact of maintenance activities was 1 2 3 4 5 considered adequate. 1C A 00000 B 00000 CO 000 12/7/1997 Positive IR 97-11 NRC Licensed operators had a good understanding of the Maintenance Rule, understood 1 2 3 4 5
how to use the matrix for taking equipment out-of-service, and understood their responsibilities for implementing the Maintenance Rule. 3B A 0 0 0 0 0 B ODOO l 1 1 CO 000 10/11/1997 VIO EEl 97-10-02, -03, Sect.
NRC Two apparent violations were identified for the failure to identify and correct a 1 2 3 4 5
08.1, pg 6-9 mispositioned EDG output breaker control switch prior to NRC identification, as well as the failure to assure adequate configuration controls of the switch position. The A 0 O 0 0 O licensee determined that the switch was most likely mispositioned as a result of someone bumping the switch. Controls for verifing the switch position were weak.
B 0 0 l 0 0 Enforcement Conference with the licensee was scheduled for 11/25/97.
C 11 11 11 o 10/11/1997 Negative SAQV IR 97-10, Sect. 07.1, pg NRC PNSC failed to review a 1996 NRC notification event (10CFR50.72) as required by 1 2 3 4 5
5-6 TS. The event involved an offsite notification to SCDEHC related to a diesel fuel oil storage tank leak. An error was made in the classification of the Condition Report A
O OD 0 0 related to the issue. Instead of Level 1, the CR was classified as Level 3, which does not get automatic review by PNSC. The inspector determined this was an BO 0 OO isolated occurrence.
C 0
00 FROM: 10/1/1997 TO: 3/23/1999 Page 5 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/11/1997 Positive IR 97-10, Sect. 02.1and NRC Walkdowns of plant electrical distribution and control room ventilation systems 1 2 3 4 5 02.2, pg 3-5 revealed that they were being operated in accordance with UFSAR and licensee lineup procedures. The systems were well maintained and TS surveillances were A 0 0 0 0 0 being met. Good licensee control and maintenance of systems important to safety.
CO 000 10/11/1997 Positive ENG IR 97-10, Sect. 01.3, pg NRC Licensee actions following the receipt of Loose Parts Monitoring alarms on SG A 1 2 3 4 5 2-3 were responsive, thorough, and indicative of strong management attention. While the source of the noise was not identified, action plans were detailed and A 0 0 0 0 0 exhaustive. Good management attention and sensitivity on potential for loose part.
C 001000 CO 000 10/11/1997 Weakness ENG URI 97-10-01, Sect.
NRC Potential discrepancies were identified in the licensee's implementation of Loose 1 2 3 4 5 01.3, pg 2-3 Parts Monitoring System implementation and FSAR commitments to RG 1.133, with regards to testing and maintenance of LPMS. Failure to implement regulatory guide A 0 0 0 0 0 commitments as described in the UFSAR.
B 1100000112 CO 000 10/11/1997 Negative IR 97-10, Sect. 01.1, pg 1 NRC Overall, control room operator logs were appropriately maintained; however, on 1 2 3 4 5 instance was noted where the status of a seismic monitor was not appropriately logged. Operator inattention to detail A 000O0 B
00 CO 000 IMAINTENANCE 8/20/1998 Positive IR-98-07 NRC The Maintenance Rule periodic assessment performed by the licensee took into 1 2 3 4 5
account SSC's performance, condition monitoring, associated goals and preventive maintenance activities and met procedural requirements.
A 000 00 B 00000 CO 000 7/27/1998 Positive IR 98-06 NRC The inspector concluded that the performance of OST-302-2 was satisfactorily 1 2 3 4 5
accomplished. Coordination of the test was good. The licensee's response to out of specification conditions was appropriate, including the entering of the required action A 0 0 0 0 0 statements. Sound engineering judgment was used to correct the out of specification conditions.
B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 6 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/27/1998 Negative IR 98-06 NRC The inspector concluded that semi-annual maintenance was satisfactorily 1 2 3 4.5 accomplished for the "B" Emergency diesel Generator (EDG). Several material and component problems were encountered during the maintenance and post A OOOO El 0 O
maintenance testing. Resolution of these problems was accomplished expeditiously and appropriately through good coordination between maintenance, engineering and B
0 0 0 0 operations personnel. The inspector identified a procedural weakness with regard to C
the disposition of test equipment during OST-409-2. The procedure did not require that the chart recorder used for capturing surveillance acceptance criteria be checked for proper set-up and programming. As a result, OST-409-2 was re performed, extending the unavailability time for the "B" EDG. The "B" EDG was retumed to operability within the required time allowed by TS (Section M3.2).
7/27/1998 NCV IR 98-06 LICENSEE A NCV for failure to install fuse clips and blown fuse indicator for the control rod 1 2 3 4 5 power supplies was identified. The failure was caused by an inadequate procedure.
Safety significance of the condition was determined to be minor (Section M3.1).
A 0 O 0
O B 00000 CO OOOl~
6/29/1998 NCV IR98-05 SELF Two orifices on the MDAFW recirculation lines that had been worked on during the 1 2 3 4 5
outage were installed backwards due to inattention to detail on the part of the mechanic. This issue was identified as a non-cited violation. The incorrectly A El O
0 0 0
installed orifices did not contribute to the pump deadheading (Section M4.1).
B 0000El CO 000 6/29/1998 Positive IR98-05 SELF The "A" motor driven feedwater (MDAFW) pump was deadheaded during a test 1 2 3 4 5
configuration. This did not cause damage to the pump. Licensee actions to determine the root cause, including formation of an event review team (ERT), were A O l O
El E appropriate.
BOOO 1O B El
[lO0OE CO 000O 6/29/1998 Positive IR98-05 SELF The repairs on the service water (SW) header were appropriately completed.
1 2 3 4 5
Management oversight of this problem was considered good (Section M2.1).
AO0O000 CO0 0
100 4/27/1998 Positive ENG IR 98-02 NRC Records of Flow Accelerated Corrosion Testing that were reviewed were found to be 1 2 3 4 5
complete and accurate. Isolated areas with below code minimum thickness were identified in Steam Generator (SG) "A" Feedwater nozzle to pipe reducer. These A OO El El O
E areas were properly evaluated by engineering and accepted for an additional fuel cycle (Sectoin M1.6).
B E l
0 C Ol 000 FROM: 10/1/1997 TO: 3/23/1999 Page 7 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/1998 Weakness ENG IR 98-02 NRC The piping modification to increase the net positive suction head (NPSH) margin 1 2 3 4 5 available to "B and "C" safety injection (SI) pumps was implemented following design specifications and applicable code requirements. Fabrication of acceptable A O0O 0 0 0 welds was accomplished with some degree of difficulty as evidenced by numerous weld rejections. Radiographs of the new welds exhibited film artifacts and the B
O 0
0 0 sensitivity on a number of films showed a need for improving the shooting technique C 0 0 0 0 and film developing practices. These observations reflected a weakness in the areas of welding and radiography (Section M1.5).
4/27/1998 Positive ENG IR 98-02 NRC The eddy current examination of SG tubes during this outage was well managed and 1 2 3 4 5
executed following approved plans, procedures and industry guidelines. Technical personnel were well qualified to perform their assigned tasks. The eddy current A 0000 [
h inspection plan and the results attained met code and industry standards. There W
were no pluggable tubes identified (Section M1.4).
B 0 0 O 0 0 CO 000 4/27/1998 Positive.
ENG IR 98-02 NRC Inservice inspection (ISI) activities observed were performed following approved 1 2 3 4 5
procedures and applicable code requirements. Technicians were well trained and qualified to perform the assigned ISI examinations. The licensee's evaluations of A 0 0 0 0 0 unacceptable field conditions were evaluated and dispositioned with conservatism (Section M1.3).
BOO 00 OO CO 000 4/27/1998 Negative IR 98-02 SELF Licensee response to the Emergency Diesel Generator problems resulting from a 1 2 3 4 5
raw water pressure switch during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance test were appropriate.
However, a more detailed and thorough investigation after the first problem (reverse A D 0 0 0 0 power trip) could have potentially identified the failure of the stopping relay (Section M1.2).
BOOOO0 CO 000 3/12/1998 Positive OPS IR 9801 NRC Changes made to maintenance and operation procedures which implemented the 1 2 3 4 5
more restrictive-requirements delineated in the new Improved Technical Specifications were found to be effective and thorough.
A OOOOD B 000001-]111:
C1 000 3/12/1998 Positive IR 98-01 NRC The process followed by the licensee in handling a pin hole leak in Component 1 2 3 4 5
Cooling Water Line 1 0-AC-41 until a code repair could be performed was correct and thorough.
A 0OOOO B 00000 C 0 000 2/2/1998 Negative IR 97-14 SELF The inspector concluded that a weakness in the post maintenance testing and 1 2 3 4 5
planning existed, which necessitated a reentry in a TS action statement following air filter replacement. However, the licensee identified several problems with post A 0 0 0 0 0 maintenance and surveillance testing that could place the unit in TS 3.0.3.
B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 8 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/22/1997 Positive IR 97-12 NRC Emergency diesel generator (EDG) maintenance management indicated advanced 1 2 3 4 5
planning and careful attention to detail. EDG post-mainenance testing was performed in a thorough and professional manner. The licensee thoroughly A 0 0 0 0 0 researched potential sources of vibration experienced.on the "B" EDG and planned further evaluations during an upcoming planned diesel maintenance outage. The B 0 0 0 O
'B' EDG vibration data exceeded the in-service limit but was well below the vendor C 0 0
0 recommended shutdown limit. 2B 12/7/1997 Positive IR 97-11 NRC Assessments of the Maintenance Rule were very good and provided effective 1 2 3 4 5
monitoring of implementation of the Maintenance Rule. Audit personnel demonstrated good knowledge of Maintenance Rule requirements. 5A/5B A 0 0 0 0 0 BOO C 0000 12/7/1997 Strength IR 97-11 NRC In general, plant material condition and housekeeping observed during walkdowns 1 2 3 4 5
was excellent. Preservation of equipment by painting was considered to be good.
The licensee initiated corrective actions for the minor discrepant conditions noted in A 0 0 0 0 0 the structural area. The overall excellent housekeeping and material condition was considered a strength. 2A BO 00 0
0 CO 000 12/7/1997 Weakness IR 97-11 NRC Industry-wide operating experience had been considered, where practical, and 1 2 3 4 5
operating data had been properly captured. However, a weakness was identified in the licensee's program in the area of collecting and tracking unavailability for safety A 0 0 0 0 0 significant SSCs. 4B/2B/3A B 00000 CO 000 12/7/1997 Strength IR 97-11 NRC For (a)(2) SSCs, in general, detailed performance criteria had been properly 1 2 3 4 5
established, suitable trending had been performed, and corrective actions were taken when SSCs failed to meet performance criteria or experienced failures. The A OO OO overall detailed program, specifically monitoring at the function level, was considered a strength. 4B/2B B
0000 0
CO 000 12/7/1997 VIO IR 97-11 NRC A violation was identified for failure to identify an unavailability period for two (a)(1) 1 2 3 4 5
Maintenance Rule components. 4B/3A A 00000 B 0000 0
CO 000 12/7/1997 Positive IR 97-11 NRC In general, operating data was being properly captured, and industry-wide operating 1 2 3 4 5
experience was considered, as appropriate. 4B/2B A 00000 B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 9 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/7/1997 Positive IR 97-11 NRC Corrective actions, goals, and monitoring were very detailed and comprehensive for 1 2 3 4 5 all (a)(1) SSCs reviewed. 4B/5A A 0000011 1 B 00000] 1 E CO 000 12/7/1997 Positive IR 97-11 NRC The licensee considered safety in establishment of goals and monitoring for the 1 2 3 4 5 (a)(1) systems and components reviewed. 4B/2B A 00000 B 0 000 CO 000 12/7/1997 Negative IR 97-11 NRC Procedural instructions to the system engineers for how to collect and track 1 2 3 4 5 unavailability time were considered weak. 4B/2B A
0000 B 00000 CO0 0100 12/7/1997 Positive ENG IR 97-11 NRC The licensee's method for balancing reliability and unavailabilty was satisfactory and 1 2 3 4 5 met the intent of paragraph (a)(3) of the Maintenance Rule. 4B/2BA 0
cO 000 12/7/1997 Positive IR 97-11 NRC The licensee's plans for performing periodic evaluations and assessments met the 1 2 3 4 5 requirements of the Maintenance Rule. 4B/2B AOOO A 00000 C
000 12/7/1997 VIO ENG IR 97-11 NRC A violation was identified for failure to include the switchyard relay building and the 1 2 3 4 5 turbine exaust hood spray system within the scope of the Rule. 4B/2BA CO0000 12/7/1997 Positive IR 97-11 NRC In general, required structures, systems, and components (SSCs) were included 1 2 3 4 5 within the scope of the Rule. 4B3/2B3 A 00000 B
CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 10 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s) 1 SMM CODES 12/7/1997 Positive IR 97-11 (Maintenance NRC Overall, the inspection team concluded that the licensee had a comprehensive 1 2 3 4 5 Rule Team Inspection)
Maintenance Rule program that met the requirements of 10 CFR 50.65, and the program was being effectively implemented. 4B1/2B A 0 0 O 0 a 00000 CO 000 10/11/1997 Strength IR 97-10, Sect. M1.2, pg NRC The licensee's process for incorporating PSA/PRA information in the planning of 1 2 3 4 5
10-11 online maintenance activities was considered a strength. Management has a strong commitment to utilizing PSA/PRA information in the planning and implementation of A 0 0 0 0 0 maintenance.
CO 000 ENGINEERING~
7/27/1998 NCV IR 98-06 LICENSEE A NCV for failure to maintain operable inside containment purge valves when the 1 2 3 4 5
open travel limits were found set greater than 70 degrees in violation of TS 3.6.3 was identifed. Licensee Event Report 98-01-01 issued for this event was closed (Section A O 0 0 0 E8.7).
1 0 0 0 0 C 00000 7/27/1998 Negative IR 98-06 NRC The inspector concluded that the NAS assessment was thorough, which resulted in 1 2 3 4 5
the identification of several deficiencies. The safety significance of the inadequate Net Positive Suction Head (NPSH) for the charging pumps under certain conditions A OO O 0 0 was minor as they are not relied upon during accident mitigation. However, the deficiency highlighted weaknesses in the design control process. Specifically, the B 0 O D
0 0 responsible engineer as well as the reviewers had failed to recognize the impact on 0
0 0 [
the charging pumps during the ongoing efforts to address the Safety Injection (SI)
NPSH issues following the Architect/Engineer inspection (Section E4.1).
4/27/1998 Positive IR 98-02 NRC The licensee's program for inspection of the containment vesssel liner was 1 2 3 4 50 effectively implemented. The results of the inspections showed that the liner met design requirements (Sectoin E2.1).
A 00000 B 00000 CO 000 4/27/1998 Positive IR 98-02 NRC Activities for correcting the instrumentation sensing line slope were performed in a 1 2 3 4 5
technically and administratively acceptable manner (Section E1.3).
A 0
0 0
0 0
B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 11 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/1998 Positive IR 98-02 LICENSEE Licensee appropriately evaluated the condition involving missing reactor coolant 1 2 3 4 5
pump diffuser cap screws that was identified during the outage. The evaluation included the potential impact of the loose parts that were created by virtue of the A
0 0 0 0 missisng cap screws on the reactor coolant system pressure boundary as well as fuel integrity as well as operating the reactor coolant pump with less than 16 diffuser B 0 0O 0 0 cap screws (Section E1.1).
C0 0
3/12/1998 VIO IR 98 01 NRC A violation was identified with three examples of failure to update the UFSAR in 1 2 3 4 5
accordance with 10 CFR 50.71 (e). A non-cited violation was also identified for the six examples of licensee identified UFSAR discrepancies discussed in IR-50-261/97-A 0 0 0 0 0 201 (Section E8.1).
cO 000 3/12/1998 Negative IR 98-01 LICENSEE The I&C technician exhibited good questioning attitude when he noticed that the 1 2 3 4 5
Ronan I/P had behaved differently than what he had remembered from a previous conversation with the responsible engineer. A non-cited violation was identified for A 0 0 0 0 0 not adequately considering the failure modes associated with the installation of new Ronan I/P. Upon identification, the licensee immediately stopped the installation B OO 0 0 activity and reconsidered the merits of the ESR as written (Section E3.1).
C 0 0 0 3/12/1998 Strength IR 98-01 NRC Based on the NRC inspections of the licensee's implementation of GL 89-10 and on 1 2 3 4 5 the licensee's commitments in its letter dated February 20, 1998, the NRC is closing its review of the GL 89-1 0program at Robinson (Section E1.2).
A 0 0 0 0 0 B 00000 CO 000 1/9/1998 EEI IR 98-03 NRC An apparent violation (3 level IVs) for inadequate design control.
1 2 3 4 5
A 00000 B 00000.
cO 000 1/9/1998 EEl IR 98-03 NRC An apparent violation (level Ill) for deficiencies in NPSH resulting in the safety 1 2 3 4 5 injection pumps failing to meet the operability requirements of the Technical Specifications and the design bases for the pumps.
A 0 0 0 0 0 B OOOOO CO 000 1/9/1998 VIO IR 98-03 NRC A corrective action violation for failuring to ensure proper cable separation for the 1 2 3 4 5 safety injection pumps.
A 00000 B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 12 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
- ROBINSON, 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/9/1998 VIO IR 98-03 NRC A violation of 10 CFR 50.59 for increasing the motor operator stroke times for two 1 2 3 4 5
valves in excess of the times specified in the UFSAR.
A 00000 B 00000 CO 000 1/9/1998 VIO IR 98-03 NRC A violation for failure to report peak cladding temperature changes as required by 10 1 2 3 4 5
CFR 50.46.
A 00000 B 00000 CO 000 1/9/1998 VIO IR 98-03 NRC A violation for inadequate corrective action to resolve instrument line slope 1 2 3 4 5
deficiencies.
A 00000 B 00000 CO 000 12/22/1997 VIO IR 97-12 NRC A Violation was identified for the failure to adequately control post modification 1 2 3 4 5
testing related to ESR 9500783. The post-modification testing failed to confirm that the cooling performance of the Containment Air Recirculation Cooling system was A 0 O OO D not adversely impacted, and that the system was capable of meeting its intended safety function as described in Section 9.4.3.1 of the licensee's UFSAR. 2B B
0 0 0 0 CO 000 12/22/1997 MISC IR 97-12 NRC The licensee had not met its original commitment date for correcting adverse 1 2 3 4 5 findings regarding its implementation of Generic Letter (GL) 89-10 identified during NRC Inspection 50-261/96-12. Progress toward correcting the findings by the new A 0 0 0 0 date proposed by the licensee was generally satisfactory. Some concerns were identified. These concems and the outstanding findings from rpt 97-12 will be re-B 0 00 0 0 examined in a future insp which will assess the licensee's completion of GL8910.
C 0 0 0 0 (2B) 12/7/1997 Strength MAINT IR 97-11 NRC System engineer's knowledge of their systems and the Maintenance Rule was 1 2 3 4 5 excellent. They understood how to apply the Maintenance Rule to their systems and were proactive in taking corrective actions. The system engineering area was A 0 0 0 0 0 considered a strength. 3B B 00000 CO 000 12/7/1997 Positive OPS IR 97-11 NRC The licensee's process for ensuring that critical safety functions were available 1 2 3 4 5 during planned outages was adequate. The use of Equipment Out-Of-Service (EOOS) Monitor to evaluate plant configurations was good. 1C A 0 0 0 0 0 B 00000 CO 0 00 FROM: 10/1/1997 TO: 3/23/1999 Page 13 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/7/1997 Strength OPS IR 97-11 NRC The approach, under paragraph (a)(3) of the Rule, to assessing the risk-impact of 1 2 3 4 5 maintenance activities was good. The assignment and use of licensed operators in the planning process and to perform evaluations of planned configurations was a A O 0 0 0 0 strength. 4B/2B CO 000 12/7/1997 Positive MAINT IR 97-11 NRC The approach to risk-ranking for the Maintenance Rule was adequate. 4B/2B 1 2 3 4 5 A 00000 B 00000@
CO 000 12/7/1997 Positive MAINT IR 97-11 NRC The expert panel committee meeting discussions on covered topics were good, and 1 2 3 4 5 the expert panel meeting minutes were well documented. 3A A 00000 B 00000 CO 000 12/7/1997 Positive OPS IR 97-11 NRC The method of assuring the assumptions for reliability and availability in the PRA are 1 2 3 4 5 conserved was good. 4B/2B A 00000 B 00000 C1 0
0 12/7/1997 Positive MAINT IR 97-11 NRC The overall quantitative approach used to perform risk ranking for SSCs in the scope 1 2 3 4 5
of the Maintenace Rule was good. Performance criteria were established with substantial probabilistic risk assessment (PRA) input. Documentation of PRA input A 0 0 0 0 0 was good. 4B/2B B 00L000 CO 000 10/11/1997 NCV NCV 97-10-05, Sect.
LICENSEE An NCV was identified against 10CFR50, App. B, Criterion III, Design Controls, for 1 2 3 4 5
E8.1, pg 14-15 the lack of adequate design controls related to the licensee's repairs and alterations to the ECCS sump screens that resulted in degraded sump conditions. This issue AOOO0 0 0O was originally identified as URI 50-261/96-12-08.
CO 000 10/11/1 997 VIO EEl 97-10-04, Sect. E2.2, LICENSEE Licensee actions upon discovery of USQ associated with certain SF shipping 12 34 5
pgl3-14 activities were adequate. An apparent violation was identified for the failure to meet 50.59 requirements for performing a change to shipping procedures involving a ADOO 00 USQ Apparent violation was reviewed by NRC management and addressed in 11/7/97 correspondence where the NRC exercised enforcement discretion from BOO 0 0 0 issuing a violation O
0 0 0 FROM: 10/1/1997 TO: 3/23/1999 Page L4Iof 19 FOR PUBLIC Re LEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(S)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/11/1997 Strength IR 97-10, Sect. E2.1, pg NRC Licensee management asked probing questions during maintenance rule system 1 2 3 4 5
12 review meetings that were recently initiated. The reivews sensitized appropriate managers to the problems related to the systems. Maintenance rule system reivew A 0 0 0 0 0 meetings should result in better focus and management of problems related to maintenance rule plant systems.
B OOOOO CO 000 10/11/1997 Positive MAINT IR 97-10, Sect. E1.1, pg NRC The spent fuel pool anti-siphon modification was properly implemented including 1 2 3 4 5
11-12 adequacy of 10CFR50.59, UFSAR updates, and post-mod. testing. This modification further enhances plant safety, in that, it eliminates the potential for a A 0 0 0 0 0 siphon induced draindown of the spent fuel pool.
C 0000 PLANTSUPPORT 8/20/1998 Positive IR-98-07 NRC The annual radiological effluent report met applicable requirements and no adverse 1 2 3 4 5
trends in radiological effluents were identified. All radiological effluents were well within release limits.
A 00 00 B 00000 C 0 000 8/20/1998 Positive IR-98-07 NRC The radiological effluent monitors and site meterological station were adequately 1 2 3 4 5
maintained.
A 00000 B OOOOO C 0 000 8/20/1998 Positive IR-98-07 NRC The liquid and gaseous radioactive waste systems were adequately maintained.
1 2 3 4 5 A 00000 B 00000 CB 000 8/20/1998 Positive IR-98-07 NRC The inspectors found the operation.of the ISFSI in conformance with the 1 2 3 4 5 commitments and requirements contained in the site specific ISFSI license and technical specifications.
A 00000 B 00000 CO 000 8/20/1998 Positive IR-98-07 NRC Radioactive waste and radioactive material transportation documentation met 1 2 3 4 5 licensee, NRC, and DOT regulatory requirements. Reviewed shipping documentation and records were properly completed. Staff responsible for A 0 0 0 0 0 preparing shipments of radioactive waste and material were qualified to perform transportation responsibillities.
BOO 0 c O 000 FROM: 10/1/1997 TO: 3/23/1999 Page 15 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 8/20/1998 Positive IR-98-07 NRC Solid radioactive waste generation and disposal were effectively monitored and 1 2 3 4 5
managed. Licensee procedures for the-control and packaging of solid radioactive waste met applicable regulatory requirements. Licensee radioactive waste streams A 0 0 0 0 0 were properly characterized.
c 0 000 8/20/1998 Positive IR-98-07 SELF The inspector determined that the licensee's T&QP was adequate, that 1 2 3 4 5
securitypersonnel were trained and qualified and that the training was documented as required by the T&QP. (Section S5).
A O 0 00 0 B
CO 000 8/20/1998 Positive IR-98-07 SELF The SFMs adequately demonstrated that they had the requisite knowledge 1 2 3 4 5
necessary to effectively implement the duties and responsibilities associated with their day-to-day and contingency response positions.
A 0 0 0 0 0 B 00000 CO 900 8/20/1998 Positive IR-98-07 SELF The licensee had developed very good procedures which clearly defined the actions 1 2 3 4 5
to be taken by the officers during normal day-to-day operatoins and emvergency contingencies. The licensee was maintaining an appropriate safeguards event log A 0 0 0 0 O and were appropriately documenting failures of security personnel and equipment.
The security failures were being appropriately analyzed and appropriate actions had BOOOOO been taken on each logged event. (Section S3).
C[
0 0
8/20/1998 Positive IR-98-07 SELF The licensee implemented proper compensatory measures during security 1 2 3 4 5
equipment malfunctions or when the security system became inoperative due to weather related events. (Section S1).
AOO 0 00 B
CO 000 6/29/1998 Strength IR98-05 NRC Overall, as-low-as-reasonably-achievable (ALARA) planning efforts were appropriate 1 2 3 4 5
and were effectively implemented for most outage work activities. Unanticipated problems and poor planning resulted in excess dose of 13 person-rem for theee of A 0 0 0 0 0 the thirty-one planned projects (Section R1.2).
B 0000 0
CO 000 6/29/1998.
Positive IR98-05 SELF The effectiveness of the licensee's dose reduction efforts in non-outage periods 1 2 3 4 5
during 1997 were very good and had resulted in the site's lowest annual collective dose. The 1997 collective dose was 13 person-rem (Section R1.2).
A 000 0 0 B 00000 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 16 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 6/4/1998 Positive IR 98-10 NRC Extensive corrective actions had been performed at the Corporate Office relating to 1 2 3 4 5 the current Access Authorization (AA) and Fitness For Duty (FFD) programs which were considered excellent. The licensee had currently implemented and staffed an A 00000 organization that was very capable of managing and implementing the AA and FFD program requirements. The sites were currently very capable of continuing to BOOOOO provide assurance that the personnel who were granted unexcorted access to the nuclear facilities met regulatory requirments. The AA/FFD audits were considered a strength.
4/13/1998 Strength IR 98-04 NRC The licensee's response strategy for protection of the vital equipment was very well 1 2 3 4 5 planned and the execution was excellent during three table-top drills and one actual drill.
AOOOOD B O 00 4/13/1998 NCV IR 98-04 SELF Alarm station and access control operators were well trained and responded to all 1 2 3 4 5
alarms and assessments as required. On November 19. 1997, for approximately seven hours, the protected area perimeter intrusion detection system microwave ADOOO 0 zone (ALMWABZ-1) was inoperative without proper compensatory measures being implemented. This resulted in Non-Cited Violation (NCV) 50-261/98-04-01.
BOOOOO CO 000 4/13/1998 Strength IR 98-04 NRC Performance testing of the licensee's access control, personnel entry, intrusion 1 2 3 4 5 detection, alarm station and alarm assessment equipment verified that the licensee had developed and employed a very good day-to-day security system that met the A DO OO O El El licensee's Physical Security Plan and Procedures requirements.
BOOOOO CO0 0100 3/12/1998 Strength IR 98-01 NRC Overall licensee performance in 1997 in the Radiological protection area was 1 2 3 4 5
excellent (Section R1.2) as evidenced by the low annual exposure.
AOOOOO BOOOOO c E 000 12/31/1997 Strength IR 97-13 NRC The controller/evaluator organization conducted an excellent critique process. TC 1 2 3 4 5
A 00000 B 0000 O
CO 000 12/31/1997 Strength IR 97-13 NRC Emergency Response Facilities were organized, equipped, and maintained in a 1 2 3 4 5 manner that provided for the emergency response. 1C A 0 00El B OO Ol 0 0 FROM: 10/1/1997 TO: 3/23/1999 Page 17 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/31/1997 Strength IR 97-13 NRC The Joint Information Center and its staff were activated and functioned in a manner 1 2 3 4 5
that provided for the dissemination of coordinated and accurate information to the public via the news media. 1C A
0000 B 000O0 CO 000 12/31/1997 Strength IR 97-13 NRC Provisions existed for the prompt communications among principal response 1 2 3 4 5
organizaitons to emergency personnel, and they were effectively used during the exercise to provide timely information and coordinate emergency response. 1C A 0 0 0 0 0 B 000000 CO 000 12/31/1997 Strength IR 97-13 NRC The licensee demonstrated the ability to make timely and concise initial and follow-1 2 3 4 5
up notifications to the States and counties. 1C A 0OO0 BOOOOO CO 000 12/31/1997 Weakness IR 97-13 NRC The licensee had a standard system for emergency classifications and used it to 1 2 3 4 5
effectively classify the off-normal events. An Exercise Weakness was identified for failure to promptly declare a Notification of Unusual Event. 1 C A OO 0 0 B OOOOO CO 000 12/31/1997 Strength IR 97-13 NRC Predesignated personnel with well defined responsibilities prompity staffed the 1 2 3 4 5 Emergency Response Facilities. 1C A 0000 B 000000 CO 000 12/31/1997 Strength IR 97-13 NRC The scenario developed for this exercise was effective for testing the integrated 1 2 3 4 5 emergency response capability and exercise preparations were well organized. 1 C AOOO B 00000 CO 000 10/11/1997 Positive IR 97-10, Sect. S1.2, pg NRC The licensee completed construction upgrades of the security firing range training 1 2 3 4 5 16-17 facility. The licensee's efforts to upgrade the training facility was indicative of good management support to further enhance security personnel performance.
A 00O OD B OO00 CO 000 FROM: 10/1/1997 TO: 3/23/1999 Page 18 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON 23-Mar-99 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SIMM CODES 10/11/1997 Positive IR 97-10, Sect. R1.2, pg NRC The licensee's corrective actions for problems related to personnel entering the 1 2 3 4 5
16 Radiation Control Area included the implementation of new turnstiles at the Radiation Control Area to provide greater positive controls. The licensee's corrective A OO0O0 actions for problems related to personnel entering the RCA without appropriate monitoring was considered aggressive.
B OOOO CO 000 SMM Template Codes:
SALP Functional Areas:
ID Code:
1A OPERATION PERFORMANCE - Normal Operations LICENSEE LICENSEE 18 OPERATION PERFORMANCE - Operations During Transients ENG ENGINEERING NRC NRC 1C OPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SELF SELF-REVEALED 2A MATERIAL CONDITION - Equipment Condition OPS OPERATIONS 2B MATERIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A HUMAN PERFORMANCE - Work Performance SAQV SAFETY ASSESSMENT & OV 3B HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE-Work Environment 4A ENGINEERING/DESIGN - Design 48 ENGINEERING/DESIGN - Engineering Support 4C ENGINEERING/DESIGN -
Programs and Processes 5A PROBLEM IDENTIFICATION & SOLUTION - Identification 58 PROBLEM IDENTIFICATION & SOLUTION - Analysis 5C PROBLEM IDENTIFICATION & SOLUTION - Resolution 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. Before the NRC makes Its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
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.
However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
FROM: 10/1/1997 TO: 3/23/1999 Page 19 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/1998
ROBINSON INSPECTION PLAN INSPECTION NUMBER OF PLANNED PROCEDURE/
TITLE/PROGRAM AREA INSPECTORS INSPECTION DATES TYPE OF INSPECTION TEMPORARY COMMENTS INSTRUCTION IP 37550/37001 Engineering 3
6/99 Core Inspection 2 weeks IP 62700 Maintenance 1
6/99 Regional Initiative Inspection (I&C Surveillance testing / calibration)
IP 81700 Security 1
7/99 Core Inspection NUREG-1021 Initial Examination 3
7/99 Preps 7/99 Initial Examination IP 84750/86750 Radiation Protection 1
8/99 Core Inspection IP 83750/60855 Radiation Protection 1
10/99 Core Inspection IP 73753 Maintenance 1
10/99 Core Inspection (outage ISI)
12/99 Core Inspection