ML14314A736
| ML14314A736 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/25/1998 |
| From: | Brian Bonser NRC/RGN-II, NRC/IE |
| To: | Young D Carolina Power & Light Co |
| References | |
| NUDOCS 9812040231 | |
| Download: ML14314A736 (26) | |
Text
November 25, 1998 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:
INSPECTION PLAN - H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2
Dear Mr. Young:
On November 2, 1998, the NRC staff completed an inspection resource planning meeting. The staff conducted this review for all operating nuclear power plants in Region II to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the staff has moved to February 1999 because of the agency's shift to an annual Senior Management Meeting cycle.
This letter advises you of our planned inspection effort resulting from the inspection planning meeting. We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite. Enclosure 1 details our inspection plan for the next 4 months. We have provided the rationale or basis for each inspection outside the core inspection program so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.
During the scheduling cycle, we will continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. We will notify you at least 3 weeks before the start of these inspections.
The NRC's general policy for reactor inspections is that we will announce each inspection, unless announcing the inspection could compromise the objectives of the inspectors.
Therefore, we may not have included some specific inspections on Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced. contains a historical listing of plant issues, called the Plant Issues Matrix (PIM).
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Carolina Power & Light. This material will be placed in the public document room.
9812040231 981125 PDR ADOCK 05000261 0
CP&L 2
We will inform you of any changes to the enclosed inspection plan. If you have any questions, please contact me at (404) 562-4560.
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. Inspection Plan
- 2. Plant Issues Matrix cc w/encls:
J. W. Moyer Director, Site Operations Carolina Power & Light Company H. B. Robinson Steam Electric Plant 3581 West Entrance Road Hartsville, SC 29550 Tom Walt Plant General Manager Carolina Power & Light Company H. B. Robinson Steam Electric Plant 3581 West Entrance Road Hartsville, SC 29550 D. B. Alexander, Manager Performance Evaluation and Regulatory Affairs CPB 9 Carolina Power & Light Company P. 0. Box 1551 Raleigh, NC 27602-1551 H. K. Chernoff, Supervisor Licensing/Regulatory Programs Carolina Power & Light Company H. B. Robinson Steam Electric Plant 3581 West Entrance Road Hartsville, SC 29550 cc w/encls continued: See page 3
CP&L 3
cc w/encls: Continued Richard Warden, Manager 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 William D. Johnson Vice President & Senior Counsel Carolina Power & Light Company P. 0. Box 1551 Raleigh, NC 27602 Karen E. Long Assistant Attorney General State of North Carolina P. 0. Box 629 Raleigh, NC 27602 Robert P. Gruber Executive Director Public Staff - NCUC P. 0. Box 29520 Raleigh, NC 27626-0520 Public Service Commission State of South Carolina P. O. Box 11649 Columbia, SC 29211 Hartsville Memorial Library 147 W. College Avenue Hartsville, SC 29550
CP&L 4
Distribution w/encls:
L. Plisco, Rll M. Ernstes, Rll R. Subbaratnam, NRR J. Coley, Rll R. Baldwin, Rll J. Lenahan, Rll F. Wright, RIl D. Thompson, RIl D. Jones, Rll PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 2112 West Old Camden Road Hartsville, SC 29550 OFFICE RII:DRP RI RII:DR RII:DRS RII:DR RIlpRS SIGNATURE NAME Gm~iacDo aid alt Gelisl P
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ROBINSON INSPECTION PLAN INSPECTION NUMBER OF PLANNED PROCEDURE/
TITLE/PROGRAM INSPECTORS INSPECTION TYPE OF INSPECTION TEMPORARY AREA DATES COMMENTS INSTRUCTION IP 81700 Physical Security 1
12/07-11/98 Core Inspection IP 62700 Maintenance 1
1/25-29/99 Initiative Inspection IPE/PRA (Intersystern LOCA)
Significance IP 71001 Operator Requalification 1
1/25-29/99 Core Inspection IP. 83750 Radiation Protection 1
3/8-12/99 Core Inspection IP 64704 Fire Protection 1
3/15-19/99 Core Inspection TI 2515/138 Operator Workarounds 3
3/15-19/99 Initiative Inspection Enclosure I
Page:
l of 2 United States Nuclear Regulatory Commission Date: 1423s/4 Region 11 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: 48 A review of the Auxiliary Feedwater (AFW) system determined that the system was capable of performing its See:
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 operating Sec:
Sec: 4A pressure and low pressure alarm concluded that the plant change was performed In accordance with engineering modification package requirements.
Ter:
09/12/1998 1998008 Pri: ENG NRC POS Pri: 5A A licensee operability determination for an Emergency Diesel Generator (EDG) Service Water piping Sac:
Sac: 4A configuration found to be different than the original design was thorough. The piping maintained structural integrity and EDG operability was not affected.
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 Sec:
Sec:
Increased stroke time previously experienced was apparently the result of a measurement error. The retesting of valve CC-749A could have been performed In a more timely manner.
Ter:
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 to Sec:
Sec: SA 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: ]A 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:
09/12/1998 1998008 Pri: PLTSUP NRC POS Pri: 3A Radiological controls utilized during a Chemical and Volume Control System filter replacement were effective in Sec:
Sec: 1C minimizing personnel exposure and contamination.
Ter:
EnJcosure 2 Item Type (Compliance, Followup,Other), From 10/01/1997 To 09/12/1998
Page: 20t2 Dt:1/519 United States Nuclear Regulatory Commission Date: 14326409 PLANT ISSUE MATRIX By Primary Functional Area Legend Type Codes:
Template Codes:
Functional Areas:
BU Bulletin IA Normal Operations OPS Operations CDR Construction 1B Operations During Transients MAINT Maintenance DEV Deviation IC 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 P21 Part 21 5C Resolution POS Positive ID Codes:
SGI Safeguard Event Report NRC NRC STR Strength Self Self-Revealed URI Unresolved item L
VIO iolaionLicensee 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.
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 PIM entries may be modified when the final conclusions are made.
Item Type (Compliance,Followup,Other), From 10/01/1997 To 09/12/1998
United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES OPERATIONS 1
9/3/98 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.
ADO 0 EO B EEED1 -10Ee CE11 El Ell 9/3/98 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 El El El D in incorrectly determining bypass valve position.
B 0El0EEl C 11El El EE 8/20/98 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 El E O O El0 plant operations and safety. Corrective actions were generally thorough, although two examples were identified where the corrective actoins were not totally effective.
B E El El El Defect repetitiveness, system and component operability, and industry events, when required, were addressed in each of the CRs reviewed.
8/20/98 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 El 0 El 0 CE El0 8/20/98 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 E El El were generally satisfactory. Management demonstrated a proactive attitude with respect to self -assessments and corrective actions.
BO OOO El E CE 0El 8/20/98 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 El El El El El 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 El El El 0 El cO EOEl FROM: 10/1/97 TO: 11/16/98 Page 1 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 8/20/98 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 U El 0 El 0 action program. Probabilistic Safety Assessments were effectively used in work control management.
BOO O
ElOElEl CO0 ElEl 7/27/98 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 El 0 B El ElEl l1l C El El 0l 6/29/98 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 Ell00000l B E11:1EllEl C El El El l 6/29/98 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 E El El El E uneventful (Section 02.1).
CO 000 C El 0El lD 6/29/98 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 El E El El E result of the seismic event. Operator performance during startup was considered good (Section 01.3).
B 0 0 El 0 C 1l El l[J@
6/29/98 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 El El El El radioactivity would have been contained, due to containment closure requirements during fuel movement. Licensee follow up to this event was appropriate (Section B
El El 0 El 01.2).
CEl ElEl l 4/27/98 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 El0000ElC B
0 00ElEl CO El l T FROM: 10/1/97 TO: 11/16/98 Page 2 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/98 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 P O3 0 El El exhibited by operations that contributed to this event (Section 01.4).
BEl El ElEl 1l 4/27/98 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 E0.0 El B ElEl000E C 0 El0 4/27/98 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).
A 0El0ElEl B El ElIEl Ell C El 0E E 4/13/98 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 0El0ElElEl B
0El 0ElEl C E El El El 4/13/98 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 El El El El nuclear instrument testing. (Section 05.3) c 0El0El00 4/13/98 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 El El 0 E 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 El 0 El El 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 C
and basis for rod insertion limits following a turbine runback and boric acid addition following two stuck rods. (Section 05.3)
FROM: 10/1/97 TO: 11/16/98 Page 3 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/13/98 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
O El El O El contained incomplete answers, resulting in licensee generated post-examination comments. (Section 05.2)
B 0 0 El El C E El 0lE3 4/13/98 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. (Section 01.1)
A 0 El 0 El B 00El0EEl0 C El El ElEA 4/13/98 Negative IR 97-14 SELF The licensee promptly and adequately implemented and planned corrective actions 1 2 3 4 5
to return the "A" Emergency Diesel Generator to operable status following inadvertent wetting of equipment due to inappropriate valve lineup on the service A 00 0
0 0 water system (Section 02.1).
C El El El El 4/13/98 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 A El El 0 El El safety implications were minimal due to plant procedures specifically prescribing the correct heatup and cooldown limits (Section 01.2).
B El El 0 0 CEl El00 12/22/97 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 El El El 0 El the UFSAR and other licensing documents previously identified during the NRC's Architectural Engineering (A/E) Team Inspection. 4B O
El El COl EOl 12/22/97 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 El El El El El strong oversight of licensee activities. A NAS assessment of the Robinson Moter Operated Valve program was thorough and resulted in important findings. IC B El El El El El CEl ElEl 12/22/97 Positive IR 97-12 NRC The licensee's implementation and transition to the Improved Technical 1 2 3 4 5
Specifications was good. iC A E 0El0Ell B El ElEl El 1 C l 0El0El FROM: 10/1/97 TO: 11/16/98 Page 4 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/22/97 Positive IR 97-12 NRC Overalt, licensee implementation of cold weather protection activities was 1 2 3 4 5 satistactory and the system engineer was familiar with plant cold weather protection equipment. Additionally, a Nuclear Assesment Section (NAS) audit of the plant cold A 121 El E0 El El weather protection activities was thorough, and condition reports were appropriately lE initiated to address several diticiencies that were identified by the NAS audit. 1lA 13 0 El El lE C0 El 0Ell 12/22/97 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 PTS) surveillance requirements. While individually, each of these items had low satety consequence, A 0 El El El El they indicated weaknesses in operator log keeping accuracy and operator attention to detail. 1A/3A B EL El El 0EI CO Elj 0 12/22/97 Positive H 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 trom a similar A El 1 0 El ElE condensate pump shatt tailure that occurred in 1991 resulted in the subsequent failure on November 16, 1997. 1lB/5C B [L1 El El El C l El El 1l 12/7/97 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 10/11970Vl B 0000l1l3 C El El El l 12/7/97 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 tor taking equipment out-of-service, and understood their responsibilities tor implementing the Maintenance Rule. 3B3 A El El El El El B El 97El-NRCEl C 9-NRCIA 10/11/97 VIO EEI 97-10-02, -03, Sect.
NRC Two apparent violations were identified for the tailure 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 tailure to assure adequate configuration controls of the switch position. The A 0 El 0 El icensee determined that the switch was most likely mispositioned as a result of someone bumping the switch. Controls for veiling the switch position were weak.
B El E ll Entorcement Conference with the licensee was scheduled tor 11/25/97.
C El El El El 10/11/97 Negative SAOV IeR 97-10, Sect. 07.1, pg NRC PNSC tailed to review a 1996 NRC notification event (100FR5N.72) as required by 1 2 3 4 5 5-6 TS. The event involved an oftsite notification to SCDEHC related to a diesel fuel oil storage tank leak. An error was made in the classification ot the Condition Report A
l El El e
E 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 B Elw El El E isolated occurrence.
C ElT S
El FROM: 10/1/97 TO: 11/16/98 Pagei d
of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/11/97 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 0l El 0 being met. Good licensee control and maintenance of systems important to safety.
B 00000~l~
C El 0El 0~
10/11/97 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 El El El 0 0 exhaustive. Good management attention and sensitivity on potential for loose part.
B 1:1El E] El C El El El~l 10/11/97 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 0l 0 0 0 0 commitments as described in the UFSAR.
B El lOEl E 10/11/97 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 El0 OElEl B E 00000El CO 000 MAINTENANCE 8/20/98 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 ElElElElEl s El ElElEl C El El ElEl 7/27/98 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 E 0
0 0 statements. Sound engineering judgment was used to correct the out of specification conditions.
B El 0l0 El CEl El00 FROM: 10/1/97 TO: 11/16/98 Page 6 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/27/98 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 C3 1E 0 El 0 maintenance testing. Resolution of these problems was accomplished expeditiously and appropriately through good coordination between maintenance, engineering and B El El El El operations personnel. The inspector identified a procedural weakness with regard to El El El 0 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 returned to operability within the required time allowed by TS (Section M3.2).
7/27/98 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 El El El El El B El 0E0 0 0 CO El 00El 6/29/98 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 0 O O E installed orifices did not contribute to the pump deadheading (Section M4.1).
CO 0[n00 6/29/98 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 El E El El El appropriate.
C 1l El El l 6/29/98
. 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).
A 0 0El-0El B 000l ll00 C El El El El 4/27/98 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 E E El El El areas were properly evaluated by engineering and accepted for an additional fuel cycle (Sectoin M1.6).
B 0 l El0 El CE El : El FROM: 10/1 /97 TO: 11/16/98 Page 7 of 19 FOR PUBLIC RELEASE Last Updated:. 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/98 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
11 El 0 CE3E 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 El El El 3 El sensitivity on a number of films showed a need for improving the shooting technique and film developing practices. These observations reflected a weakness in theC l
EEll areas of welding and radiography (Section M1.5).
4/27/98 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 El El El El El inspection plan and the results attained met code and industry standards. There were no pluggable tubes identified (Section M1.4).
B LJLiOEW C 0l El Ell 4/27/98 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 qualitied to perform the assigned so examinations. The licensee s evaluations of A El El El E El unacceptable field conditions were evaluated and dispositioned with conservatism (Section M1.3).
B 5)El.E1 El C 1l El Ell 4/27/98 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 E 0 El El El power trip) could have potentially identified the failure of the stopping relay (Section M1.4).
C El El 1l E 4/13/98 Negative IR 97-14 SELF The inspector concluded that a weakness in the post maintenance testing and 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 El El E El 0 maintenance and surveillance testing that could place the unit in TS 3.0.3.
B El E El olA C 1l El El El 3/12/98 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 El El El El El B El E El El0 c E El El El 3/12/98 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 10-AC-41 until a code repair could be performed was correct and thorough.
A (lOEl0 El B121 El 11El l1l c 12 El4 FROM: 10/1/97 TO: 11/16/98 Page 8 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 12/22/97 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 1 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 I-El El 0 0E "B" EDG vibration data exceeded the in-service limit but was well below the vendor C El E El E recommended shutdown limit. 2B0 12/7/97 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 El El El El El 1B El E1 El E3 0 C El El El El 12/7/97 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 El El El the structural area. The overall excellent housekeeping and material condition was considered a strength. 2A B IO 0 0 El C 1l El El El 12/7/97 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 El El El El El significant SSCs. 4B/2B/3A C 0 El00 12/7/97 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
l El El El I0 overall detailed program, specifically monitoring at the function level, was considered a strength. 4B/2B E0l El El CEl 00El0l 12/7/97 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 0El0ElElE B El00ElEl C El El El El 12/7/97 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/28 A ElEl0ElEl B
0 EEl0El CFEl /
El El FROM: 10/1/97 TO: 11/16/98 Page 9 ot 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 12/7/97 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 E00000 E E B 112 E:1El E 12/7/97 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 00EElE00 C1 E 00 12/7/97 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 EEEE B
0 CO EEE 12/7/97 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/2B A EE00E B 1:11:1E l CO 000 12/7/97 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 A 00000 BE 00000 CO 1000 12/7/97 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/2B A 00000 B E0000 CO 000 12/7/97 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. 4B/2B A 0000 B 00E00 cO 000 FROM: 10/1/97 TO: 11/16/98 Page 10 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
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SMM CODES 12/7/97 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. 4/12B A El El O El El B El 123El 0 0 C El DElE0 10/11/97 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 El El E El El maintenance.
13 El El 0lEl C 0 El0 ENGINEERING I
7/27/98 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 AOOO E O
E8.7).
B 1 El El ElEll C El El El El 7/27/98 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 El El El 0 12 was minor as they are not relied upon during accident mitigation. However, the deficiency highlighted weaknesses in the design control process. Specifically, the B El El El 0 El responsible engineer as well as the reviewers had failed to recognize the impact on C El El ElE the charging pumps during the ongoing efforts to address the Safety Injection (SI)
NPSH issues following the Architect/Engineer inspection (Section E4.1).
4/27/98 Positive IR 98-02 NRC The licensee's program for inspection of the containment vesssel liner was 1 2 3 4
51 effectively implemented. The results of the inspections showed that the liner met design requirements (Sectoin E2.1).
A OOOOOl l1l B 00El0E 0 O COl El00 4/27/98 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).
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SMM CODES 4/27/98 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 17 0D 1:1 El El 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 El -l E:] El 0J cap screws (Section E1.1).
C El El El El 4/13/98 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 El El El El El 201 (Section E8.1).B El 0 0 E
.I CEl El IE 9 4/13/98 Negative IR 98-01 LICENSEE The a&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 El El 0 El not adequately considering the failure modes associated wih the installation of new Ronan I/P. Upon identification, the licensee immediately stopped the installation B El El El El El activity and reconsidered the merits of the ESR as written (Section E3.1).
C El E E El 4/13/98 Strength IR 98-01 NRIC Based on the N1C 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 89-10 program at Robinson (Section E1.2).
A l l 0 El B El11:lEl El C I]El El El 12/22/97 VI 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 El El El El El 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 El El El El C El El 1lE 12/22/97 MISC IR 97-12 NRC The licensee had not met its original commitment date for correcting adverse 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
El El El El date proposed by the licensee was generally satisfactory. Some concerns were identified. These concerns and the outstanding findings from rpt 97-12 will be re-B El was El El examined in a future insp which will assess the licensee's completion of L8910.
C El El El (283) 12/7/97 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 El nw El El El considered a strength. 3B an t osd fi f2 C El El El El FROM: 10/1 /97 TO: 11/16/98 Page 12 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 12/7/97 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 0l 0- 0 0 0E B
0El 0ElEl0 CO 0E00 12/7/97 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 E 0 0 0 0 strength. 4B/2B B 000ElE 1El C El 0El e 12/7/97 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 ElEl ll0 B ElO 21l-1l-1l C El El IDEl 12/7/97 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 0El0E 100 B El 0El El El C 0 ElE0 12/7/97 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 ElElEl0 B 0 001lElll C E El E 12/7/97 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 E El El El E0 was good. 4B/2B B
000 C El El IDl 10/11/97 NCV NCV 97-10-05, Sect.
LICENSEE An NCV was identified against 10CFR50, App. B, Criterion Ill, 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 A El El El 0 El was originally identified as URI 50-261/96-12-08.
CFEl El ElT FROM: 10/1 /97 TO: 11/16/98 Page 13 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 10/11/97 VIO EEl 97-10-04, Sect. E2.2, LICENSEE Licensee actions upon discovery of USQ associated with certain SF shipping 1 2 3 4 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 A El El C3 El El UISO Apparent violation was reviewed by NRC management and addressed in 1 1/7/97 correspondence where the NRC exercised enforcement discretion from B El E] El El El issuing a violation C El El 0lEl 10/11/97 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 El El El El El meetings should result in better focus and management of problems related to
-r maintenance rule plant systems.
B3 0 0 lL-JEl l C El El 1 4
10/11/97 Positive MAINT IR 97-10, Sect. El.1, pg NRC The spent fuel pool anti-siphon modification was properly implemented including 1 2 3 4 5
11-12 adequacy of 1 uoCFR5o.59, oFSAR updates, and post-mod. testing. This modification further enhances plant safety, in that, it eliminates the potential for a A El El m eet El siphon induced draindown of the spent fuel pool.
e m
dct from PLANT SUPPORT.I 8/20/98 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 ra Elt th s s
B El 0ElE]Ell C l El Cl l 8/20/98 Positive IR-98-07 NRC The radiological effluent monitors and site meterological station were adequately 2 3 4 5 maintained.
A El11El El l B El El 1El A~
C 1l El ElEl 8/20/98 Positive IR-98-07 NRC The liquid and gaseous radioactive waste systems were adequately maintained.
2 3 4 5 A 0El1El 1Ell B [3El 0El Ell C El El 0l1l 8/20/98 Positive IR-98-07 NRC The inspectors found the operation of the SF in conformance with the n 2 3 4 5 commitments and requirements contained in the site specific pSFo license and technical specifications.
A El 0E3 l1l1l B El 1ElEl Ell C 0 ElElEl FROM: 10/1/97 TO: 11/16/98 Page 14 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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ID'd ISSUE(s)
SMM CODES 8/20/98 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 ADOOOO preparing shipments of radioactive waste and material were qualified to perform transportation responsibillities.
B El El El c E El 0~
8/20/98 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 C3 El El 0 El were properly characterized.
B El 11l1El Ell E1 El 11E19l 8/20/98 Positive IR-98-07 SELF The inspector determined that the licensee's T&OP 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).
AOO El ElEl B 11El El0Ell CEl 0 ElEl 8/20/98 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 El 0 El El B ElElEEl CEl 0ElEl 8/20/98 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 El 0 El 0 El and were appropriately documenting failures of security personnel and equipment.
The security failures were being appropriately analyzed and appropriate actions had B El El El El been taken on each logged event. (Section S3).
C El l 8/20/98 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 Sl).
A ElElOElEl 0
B 0000ElElE c 0 El00 6/29/98 Positive SELF I
1 2 3 4
5 A
Ell00El B El El El P El C El El El El FROM: 10/1/97 TO: 11/16/98 Page 15 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
ROBINSON 16-Nov-98 DATE TYPE(s)
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ID'd ISSUE(s)
SMM CODES 6/29/98 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 DO O
El O
0 the thirty-one planned projects (Section R1.2).
C El El 11 E 6/29/98 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 El El 0 El El B El El El El l C El El 1 la 4/13/98 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.
A ElEl ElOEl B El El El Ell C El El 1l1 l 4/13/98 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 A El El El El El zone (ALMWABZ-1) was inoperative without proper compensatory measures being implemented. This resulted in Non-Cited Violation (NCV) 50-261/98-04-01.
B El El El El El CEl ElElEl 4/13/98 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 El El El El El licensee's Physical Security Plan and Procedures requirements.
B 000ElEl CEl El 4/13/98 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.
A El0ElElEl B 0El0 0ElEl c 0 El 000 12/31/97 Strength IR 97-13 NRC The controller/evaluator organization conducted an excellent critique process. 1C 1 2 3 4 5
A ElEl0El0 B
00El00El0 CO0 0lEl FROM: 10/1/97 TO: 11/16/98 Page 16 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 12/31/97 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 El 000 El B 11El El El 0 C El ElEEl0 12/31/97 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. 1 C A 0 0El 0 El B El 1211El El C El El 11 i
12/31/97 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. iC A El O
El El El B
00El0El0l COl ElElEl 12/31/97 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
El00El B 000EEl0El CEl ElElEl 12/31/97 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. 1C A E El El 0 El B El0 ll00 cOl El 12/31/97 Strength IR 97-13 NRC Predesignated personnel with well defined responsibilities prompIty staffed the 1 2 3 4 5
Emergency Response Facilities. 1C A 000El0El0 B
0El0 El C El 0El Ell 12/31/97 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. 1C A 00El0Ell B El ElEl ElEl CO 0El0El FROM: 10/1/97 TO: 11/16/98 Page 17 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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SMM CODES 10/11/97 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 1 0 El El El B E EEDEl 10/11/97 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 El El 0 El El actions for problems related to personnel entering the RCA without appropriate monitoring was considered aggressive.
8O OEl OElEl CEl ElEl FROM: 10/1/97 TO: 11/16/98 Page 18 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98
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ID'd ISSUE(s)
SALP Functional Areas:
ID Code:
1A OPERATION PERFORMANCE - Normal Operations LICENSEE LICENSEE 1B OPERATION PERFORMANCE - Operations During Transients ENG ENGINEERING NRC NRC iC 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 SAOV SAFETY ASSESSMENT & OV 32 HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE-Work Environment 4A ENGINEERING/DESIGN - Design 4B ENGINEERING/DESIGN - Engineering Support 4C ENGINEERING/DESIGN -
Programs and Processes 5A PROBLEM IDENTIFICATION & SOLUTION - Identification 5B 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: 10/1/97 TO: 11/16/98 Page 19 of 19 FOR PUBLIC RELEASE Last Updated: 9/3/98