ML20005E357
| ML20005E357 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/19/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Eury L CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20005E358 | List: |
| References | |
| NUDOCS 9001050107 | |
| Download: ML20005E357 (30) | |
See also: IR 05000324/1989028
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DEC 191989
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Docket Nos. 50-325, 50-324
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Carolina Power and Light Company
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ATTN:
Mr. - Lynn W. Eury
Executive Vice President
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Power Supply
P. O. Box 1551.
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Raleigh, NC 27602
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Gentlemen:
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SUBJECT:
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE
(NRC INSPECTION REPORT NOS. 50-325/89-28 AND 50-324/89-28)
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This refers to the NRC's Systematic Assessment of Licensee Performance (SALP)
for your Brunswick facility which was sent to you on November 3, 1989; our
meeting of November 9, 1989, at which we discussed the report, and your written
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connents dated December 6,1989.
4
We appreciate your suggestion to clarify the last paragraph of Section I. A
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(page 2).
The sentence has been modified to reflect your comment.
In addition
a date in the first paragraph of the same section has been corrected from
November 12, 1989 to November 12, 1988.
With this errata, the interim report
sent to you on November 3, 1989, constitutes our final SALP report.
We will monitor the implementation of the steps that are being taken to address
concerns identified in the report.
I have enclosed a sunmary of the meeting
and the slides which were used by the NRC, a copy of your written comments, and
>
the errata sheets for the Final SALP report for the period September 1,1988
through August 31, 1989.
,
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,
.
Title 10, Code of Federal Regulations, a copy of this letter with the referenced
enclosures will be placed in the NRC's Public Document Room.
No reply to this
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letter is required; however, should you have any questions concerning these
matters, I will be pleased to discuss them with you.
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Sincerely,
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Stewart D. Ebneter
Regional Administrator
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Enclosures:
(See page 2)
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9001050107 891219
ADOCK 05000324
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DEC 191989
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Carolina Power and Light Company
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Enclosures:
1.
SALP Presentation Meeting Sunnary
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and Slides
2.
Licensee Response
3.
Errata Sheets for the Final SALP
Report
Cc w/encls:
R. B. Starkey. Jr.. Manager
Robert P. Gruber-
Brunswick Nuclear Project
Executive Director
Box 10429
Public Staff - NCUC
Southport. NC 28461
P. O. Box 29520
Raleigh. NC 27626-0520
J. L. Harness
Plant General Manager
State of North Carolina
Brunswick Steam Electric Plant
P. O. Box 10429
bec w/ enc 1:
Southport. NC 28461
Document Control Desk
R. E. Jones. General Counsel
NRC Resident inspector
Carolina Power & Light Company
U.S. Nuclear Regulatory Commission
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P. O. Box 1551
Star Rte. 1. Box 208
Raleigh. NC 27602
Southport.NC 28461
Ms. Frankie Rabon
Board of Connissioners
P. O. Box'249
Bolivia. NC 28422
Chrys Bagget
State Clearinghouse
Budget and Management
116 West Jones Street
Raleigh. NC- 27603
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Dayne H. Brown Chief
' Radiation Protection Branch
. Division of Facility Services
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N. C. Department of Human Resources
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701 Barbour Drive
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Raleigh. NC 27603-2008
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H. A. Cole
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Special Deputy Attorney Genera
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ENCLOSURE 1
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SALP PRESENTATION MEETING
SUMMARY AND SLIDES
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OPERATIONS - CATEGORY 2
MANAGEMENT EFFORTS WERE SUCCESSFUL IN ARRESTING THE DECLINING TREND
OBSERVED DURING LAST ASSESSMENT PERIOD:
CHALLENGES TO OPERATOR'S EFFECTIVENESS WERE REOUCED AS EVIDENT BY A
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SIGNIFICANT DECREASE IN CONTROL BOARD TROUBLE TAGS.
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ADDITION OF EXTRA OPERATOR PER SHIFT.
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PLANT HOUSEKEEPING AND DRYWELL CLOSEOUT PROCESS CONTINUED TO BE A
STRENGTH.
LICENSED OPERATIONS STAFF CONTINUED TO PERFORM SATISFACTORILY DURING
OFF-NORMAL TRANSIENT CONDITIONS.
PROCEDURAL ADHERENCE WAS ADEQUATE WITH ONLY AN OCCASIONAL EXAMPLE OF
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FAILURE TO FOLLOW PROCEDURE.
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OPERATIONS - CATEGORY 2 (CON'T)
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ALTERNATE SAFE-SHUTDOWN PROCEDURES WERE DETAILED AND COMPREHENSIVE.
EXTENSIVE MEASURES WERE TAKEN TO IMPROVE EMERGENCY OPERATING PROCEDURES,
WITH FURTHER ENHANCEMENT UNDERWAY,
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OTHER MANAGEMENT INITIATIVES, SUCH AS A METHOD TO CAPTURE CONDITIONS
ADVERSE TO QUALITY THROUGH ASSIGNING INDIVIDUAL RESPONSIBILITY AND A
SEMI-ANNUAL REVIEW OF OPERATIONS EVENTS TO FIND OVERALL TRENDS AND SUGGEST
IMPROVEMENTS, ARE GOOD.
APPENDIX R AUDIT WAS UNTIMELY, BUT SOUND TECHNICAL JUDGEMENT WAS
DEMONSTRATED WITH RESPECT TO RESOLVING IDENTIFIED DEFICIENCIES BEFORE
RESTARTING UNIT I.
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CONTROLLING PLANT CONDITIONS FOR A SHUTDOWN UNIT CONTINUED TO BE A MAJOR
WEAKNESS.
DESPITE THE INCREASED MANAGEMENT ATTENTION IN PLANT OPERATIONS, ACTION
TAKEN WITH RESPECT TO PERSONNEL ERRORS, PARTICULARLY IN THE AREAS OF
CONFIGURATION CONTROL AND CLEARANCES, WERE YET TO BE EFFECTIVE.
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RADIOLOGICAL CONTROLS - CATEGORY 2
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THE HEALTH PHYSICS (HP) PROGRAM CONTINUED TO BE ADEQUATELY IMPLEMENTED.
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OVERALL QUALITY AND EXPERIENCE LEVEL OF HP STAFF REMAINED A PROGRAM
STRENGTH.
POSITIVE MANAGEMENT ATTENTION / SUPPORT WAS REFLECTED BY THE:
SUCCESSFUL COMPLETION OF DECHANNELING AND SUBSEQUENT SHIPMENT OF
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SPENT FUEL TO SHEARON HARRIS
IMPROVEMENTS IN EFFLUENT MONITOR OPERABILITY
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IMPROVEMENTS IN CONTROLLING PERSONNEL CONTAMINATION THROUGH THE
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ACQUISITION OF NEW IPM-8 WHOLE BODY FRISKERS
WELL DEFINED TRAINING PROGRAMS (HP AND GET) AND THE TIME ALLOCATED
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FOR EMPLOYEES TO ATTEND THE TRAINING SESSIONS.
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RADIOLOGICAL CONTROLS - CATEGORY 2 (CON'T)
THE STATION'S COLLECTIVE RADIATION DOSE REMAINED RELATIVELY HIGH, WITH
IGSCC RELATED ACTIVITIES BEING THE MAJOR CONTRIBUTOR.
MANAGEMENT'S COMMITMENT TO REPLACE RECIRCULATION PIPE IS A POSITIVE
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STEP IN REOUCING DOSE IN THE LONG TERM.
HYOROGEN WATER CHEMISTRY CONTROL WAS IMPLEMENTED IN UNIT 2 BUT NOT
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FULLY OPERATIONAL,
ACTIONS TAKEN IN RESPONSE TO NRC INITIATIVES INVOLVING ALARA
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IMPROVEMENTS
WERE
INEFFECTIVE,
LACKING
NECESSARY
MANAGEMENT
ATTENTION.
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EMERGENCY PREPAREDNESS - CATEGORY 2
THE CAPABILITY TO IMPLEMENT CRITICAL ASPECTS OF EMERGENCY PREPAREDNESS
(EP) WAS DEMONSTRATED DURING SIMULATED AND ACTUAL EMERGENCY EVENTS.
THE SITE'S EMERGENCY PLAN, EMERGENCY FACILITIES, STAFFING, AND EQUIPMENT
WAS ADEQUATELY MAINTAINED.
THE EP TRAINING PROGRAM HAD ~ EN SUFFICIENTLY CHANGED TO INCLUDE PROCTORED
EXAMS AND AUDITABLE TRAINING RECORDS.
DURING THE 1988 ANNUAL EXERCISE SOME ESSENTIAL ELEMENTS OF EMERGENCY
RESPONSE WERE IDENTIFIED AS REQUIRING IMPROVEMENT.
NOTIFICATION METHODS AND PROCEDURES
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ONSITE EMERGENCY ORGANIZATION
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EMERGENCY CLASSIFICATION SYSTEM
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CORRECTIVE ACTION WAS NOT EFFECTIVE AS EVIDENT BY THE REPEATED FAILURE TO
MAKE FOLLOWUP OFFSITE NOTIFICATIONS FROM THE CONTROL ROOM.
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MAINTENANCE / SURVEILLANCE - CATEGORY 2
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SIGNIFICANT IMPROVEMENT IN REDUCING THE NUMBER OF SAFETY SYSTEM FAILURES.
MOV PROGRAM CONSIDERED A STRENGTH.
AUTOMATED TRACKING SYSTEMS CONTINUED TO BE EXCELLENT TOOLS IN MANAGING THE
MAINTENANCE AND SURVEILLANCE OF THE STATION.
SUCH SYSTEMS WERE UTILIZED
TO IMPROVE THE IDENTIFICATION AND TRACKING 0F REPETITIVE FAILURES.
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THE MAINTENANCE AND SURVEILLANCE PROCEDURES UPGRADE PROGRAM INCLUDING
ALLOTTED RESOURCES WERE CONSIDERED GOOD.
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OUTSTANDING WORK REQUESTS / JOB ORDERS STEADILY TRENDE0 DOWNWARD.
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THE INCLUSION OF AN INFRARED THERM 0 GRAPHY PROGRAM WAS CONSIDERED AN ASSET
TO THE OVERALL MAINTENANCE PROGRAM.
OBSERVATION OF SURVEILLANCE TEST ACTIVITIES SHOWED THAT TEST PERSONNEL
WERE TECHNICALLY KNOWLEDGEABLE AND EFFECTIVE IN TEST C0 ORDINATION.
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MAINTENANCE / SURVEILLANCE - CATEGORY 2 (CON'T)
ISI ACTIVITIES ASSOCIATED WITH THE EXAMINATION OF UNIT 1 PIPING AND
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COMPONENTS FOR IGSCC WERE GOOD.
THE PROGRAM FOR UPGRADING COMPONENT IDENTIFICATION LABELING AND CORRECTING
EXISTING LABELING DEFICIENCIES WAS CONSIDERED DEFICIENT.
WEAKNESS IN THE MAINTENANCE WORK PLANNING AND PERFORMANCE PROCESS WAS
INDICATED BY THE NUMBER OF IDENTIFIED POST MAINTENANCE TEST DEFICIENCIES.
SEVERAL RECURRING MAINTENANCE RELATED SYSTEM PROBLEMS STILL LACKED THE
NECESSARY ATTENTION FOR PROMPT AND COMPLETE RESOLUTION.
SOME SYSTEMS / EQUIPMENT WERE NOT ADEQUATELY MAINTAINED - THE AUXILIARY BUS
DUCTWORK BEING ONE WHICH CONTRIBUTED TO THE UNIT 2 LOSS OF OFFSITE POWER
EVENT / MANUAL SCRAM.
CONTROL OF FUSES HAS BEEN A RECURRING PROBLEM.
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UNNECESSARY SAFETY SYSTEM ACTUATIONS OCCURRED DUE TO THE SHORTING OF
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INSTRUMENT LEADS DURING SURVEILLANCE TESTING.
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SECURITY - CATEGORY 1
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SECURITY ACTIVITIES CONTINUED TO BE A STRENGTH.
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SITE'S CONTRACT SECURITY FORCE WAS ADEQUATELY STAFFED AND
APPROPRIATELY TRAINED AND EQUIPPED.
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OBSERVED PERFORMANCE OF SECURITY
PERSONNEL
SHOWED THEM TO BE
KNOWLEDGEABLE, ALERT, AND CAPABLE.
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SECURITY MANAGEMENT CONTINUED TO BE INTIMATELY INVOLVED IN SECURITY FORCE
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ACTIVITIES, AGGRESSIVELY SEEKING EFFECTIVE AND LASTING SOLUTIONS TO
SECURITY-RELATED PROBLEMS.
TWO NON-CITED VIOLATIONS WERE IDENTIFIED AND PROMPTLY CORRECTED BY THE
LICENSEE.
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INATTENTIVE GUARD AT A DEGRADED VITAL AREA BARRIER.
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FAILURE TO REPORT ABOVE EVENT IN A TIMELY FASHION.
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ENGINEERING / TECHNICAL SUPPORT - CATEGORY 2
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PERFORMANCE WAS MIXED, WITH IMPROVEMENT EVIDENT IN THE LATTER HALF OF THE
ASSESSMENT PERIOD.
EFFECTIVE TECHNICAL SUPPCRT AND MANAGEMERT INVOLVEMENT WAS DEMONSTRATED ON
A NUMBER OF TECHNICAL ISSUES, INCLUDINE HPCI RELIABILITY IMPROVEMENTS AND
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RESOLUTION OF UNIT 1 REACTOR VESSEL N0ZZLE CRACK INDICATIONS.
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ACTIONS TAKEN IN THE LATTER HALF 0F THE ASSESSMENT PERIOD BROUGHT ABOUT
IMPROVEMENTS IN SYSTEM ENGINEERING INVESTIGATION AND
ROOT
CAUSE
DETERMINATIONS.
SIGNIFICANT PROGRESS WAS MADE TOWARDS THE REDUCTION OF THE ENGINEERING
WORK REQUEST BACKLOG, THROUGH THE COMPLETION OF THEIR INITIAL REVIEW AND
DISPOSITION.
ACTIONS TAKEN TOWARDS THE END OF THE ASSESSMENT PERIOD TO ADDRESS EWR
RELATED MATERIAL PROBLEMS AND OBSOLETE PARTS, CONFIRMED MANAGEMENT'S
INTENTIONS TO RESOLVE THIS ISSUE.
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ENGINEERING / TECHNICAL SUPPORT - CATEGORY 2 (CON'T)
OPERATOR TRAINING WAS CONSIDERED GOOD, 'wlTH A NOTED IMPROVEMENT Ii1
TRAININ6 REFERENCE MATERIAL.
MANAGEMENT WAS COMMITTED TO IMPROVING THE SI1E SPECIFIC SIMULATOR.
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LARGE NUMBER OF DEFICIENCIES WERE CORRECTED AND FURTHER CHANGES HAVE BEEN
PLANNED TO ASSURE CERTIFICATION STANDARDS ARE MET PRIOR TO THE DEADLINE.
ENGINEERING SUPPORT FOR SEVERAL SERVICE WATER ISSUES WAS NOT AGGRESSIVE.
ONCE PROMPTED BY THE NRC, HOWEVER, THE RESOLUTION OF THESE ISSUES WAS
THOROUGH.
THE PROGRAM FOR DESIGN CHANGE DEVELOPMENT WAS INADEQUATE DUE TO WEAK
DESIGN BASE INFORMA*fl0N RESOURCE, INADEQUATE INTERFACE DEFINITION,
OUTDATED-PROCEDURES, AND UNAVAILABILITY OF PRE 0PERATIONAL TEST DATA.
ADMINISTRATIVE CLOSE0VT OF SOME MODIFICATIONS WAS UNTIMELY, BEING LEFT
OPEN AFTER IMPLEMENTATION ON AN AVERAGE OF 2 YEARS.
COMRUNICATION PROBLEMS ON SOME ISSUES HINDERED PROMPT INITIAL ACTION.
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SAFETY ASSESSMENT / QUALITY VERIFICATION - CATEGORY 2
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AN INCREASED MANAGEMENT PRESENCE IN THE POWER BLOCK AND A DEMONSTRATED
WILLINGNESS TO MAKE THE HARD DECISIONS ATTRIBUTED TO THE IMPROVEMENT IN
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THIS AREA,
THE CORRECTIVE ACTION PROGRAM WAS IMPROVED THROUGH THE SITE WIDE
IMPLEMENTATION OF A CORRECTIVE ACTION PROCEDURE,
THE END OF- THE ASSESSMENT PERIOD APPOINTMENT OF A TECHNICAL ASSISTANT TO
THE PLANT GENERAL MANAGER RESPONSIBLE FOR COORDINATING THE SITE CORRECTIVE
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ACTION PROCESS WAS CONSIDERED A POSITIVE STEP.
IMPROVEMENTS WERE SEEN.IN THE LICENSEE'S ABILITY TO ADEQUATELY ASSESS THE
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SAFETY SIGNIFICANCE OF DISCREPANT CONDITIONS AND TAKE THE APPROPRIATE
CORRECTIVE' ACTION.
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ONCE AN ISSUE WAS PROPERLY CATEGORIZED AND THE APPROPRIATE LEVELS OF PLANT
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MANAGEMENT WERE AWARE, ACTIONS TO RESOLVE THE ISSUE WERE EXTENSIVE.
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SAFETY ASSESSMENT / QUALITY VERIFICATION - CATEGORY 2 (CON'T)
ONSITE QUALITY ASSURANCE ACTIVITIES WERE PROPERLY FOCUSED, WITH AN
INCREASED TREND TOWARD PERFORMANCE BASED SURVEILLANCES.
THE APPENDIX R COMPLIANCE FOCUSED CORPORATE QA AUDIT FOUND SEVERAL
SIGNIFICANT PROBLEMS.
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ON SEVERAL OCCASIONS SAFETY REVIEWS LACKED THE NECESSARY VIG0ROUS
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QUESTIONING AND WERE HAMPERED BY A FAILURE TO GET THE RIGHT PEOPLE
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INVOLVED WHEN ISSUES EMERGED.
THE ONSITE NUCLEAR SAFETY GROUP'S IMPACT ONSITE HAD DIMINISHED THIS
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-ASSESSMENT PERIOD DUE TO A REDUCTION IN STAFF,
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E'XITED STATES
XE~ CLEAR REGELATORY
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COMMISSION
SYSTEMATIC ASSESSMENT
OF
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LICENSEE PERFORMANCE
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CAROLINA POWER AND LIGHT C:'MPANY
SALP PERIOD
SEPTEMBER 1,1988 through AUGUST 31,1989
BRUISWICK DITS
1 & 2
NOVEMBER 9,1989
SOUTHPORT, NORTH CAROUNA
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SALP PROGRAM OBJECTIVES
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1. IDENTIFY TRENDS IN LICENSEE PERFORMANCE
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2. PROVIDE A BASIS FOR ALLOCATION
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3. IMPROVE NRC REGULATORY PROGRAM
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REGIONH ORGANIZATION
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ADWESTRATOR S. ENER
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PERFORMANCE AXALYSIS AREAS
FOR OPERATIXG REACTORS
A. PIANT OPERATIONS
B. RADIOLOGICAL CONTROLS
C. MAINTENANCE / SURVEILLANCE
E. SECURITY
F. ENGINEERING / TECHNICAL SUPPORT
G. SAFETY ASSESSMENT / QUALITY VERIFICATION
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AREA PERFORMAXCE
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CHEGORY 1
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UCENSEE MANAGEMENT ATTENTION- AND INVOLVEMENT
ARE READil.Y EVIDENT AND PLACE EMPHASIS ON SUPERIOR
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PERFORMANCE-0F NUCLEAR SAFETY OR SAFEGUARDS
--ACTIVTIES, WITH THE RESULTING PERFORMANCE SUB-
STANTIALLY EXCEEDING REGULATORY REQUIREMENTS.
UCENSEE
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RESOURCES ARE AMPLE AND EFFECTIVELY USED S0 THAT
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A HIGH LEVEL OF PLANT AND PERSONNEL PERFORMANCE IS
BEING ACHElVED.
REDUCED NRC ATTENTION MAY BE
APPROPRIATE.
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AREA PERFORMAXCE
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CATEGORY 2
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UCENSEE MANAGEMENT ATTENTION AND INVOLVEMENT
IN THE PERFORMANCE OF NUCLEAR SAFETY OR SAFEGUARDS
ACTMTIES ARE GOOD. THE UCENSEE HAS ATTAINED A
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LEVEL OF PERFORMANCE AB0VE THAT NEEDED TO MEET
REGULATORY REQUIREMENTS. UCENSEE RESOURCES ARE
ADEQ'JATE AND REASONABLY ALLOCATED S0 THAT GOOD PLANT
AND PERSONNEL PERFORMANCE IS BEING ACHEIVED. NRC
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ATTENTION MAY BE MAINTAINED AT NORMAL LEVELS.
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AREA PERFORMAXCE
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CATEGORY J
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UCENSEE MANAGEMENT ATTENTION AND INVOLVEMENT
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lN THE PERFORMANCE OF NUCLEAR SAFETY OR SAFEGUARDS
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ACTIVITIES ARE NOT SUFFICIENT.
THE UCENSEE'S
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PERFORMANCE DOES NOT SIGNIFICANTLY EXCEED THAT NEEDED
TO MEET MINIMAL REGULATORY REQUIREMENTS.
UCENSEE
RESOURCES APPEAR TO BE STRAINED OR NOT EFFECTIVELY
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USED.
NRC ATTENTION SHOULD BE INCREASED AB0VE
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NORMAL LEVELS.
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EVAILATIOX CRITERIA
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1. MANAGEMENT INVOLVEMENT IN ASSURING QUAU1Y
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2.. APPROACH-TO RESOLUTION OF TECHNICAL ISSUES
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FROM A SAFETY STANDPOINT
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3. RESPONSIVENESS TO NRC INITIATIVES
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4. ENFORCEMENT HISTORY
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5. REPORTING AND ANALYSIS OF REPORTABLE EVENTS
6. STAFFING (INCLUDING MANAGEMENT)
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7. TRAINING EFFECTIVENESS AND QUAUFICATION
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V 0 AT Cs
S MMARY
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spHueER 1,1988 through AUGUST 31,1940
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IV
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BRUNSMCK 1
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3
13
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LICENSEE RESPONSE
SERIAL:
.
United States Nuclear Regulatory Commission
ATTENTION: Document Control Desk
20555
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2
DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62
RESPONSE TO NRC SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE
Gentlemen:
Carolina Power and Light Company (CP&L) has reviewed the Interim
i
Systematic Assessment of Licensee Performance (SALP) Board Report.
forwarded by your letter of November 3,
1989.
CP&L has also
,
reviewed the additional NRC comments presented during the public
l
'SALP Report review meeting of November 9,
1989.
The report
l-
evaluated the performance of CP&L's Brunswick Nuclear Project
L
during the period September 1,
1988 through August 31, 1989.
~
1
'
-
The company' appreciates the NRC's efforts to present a balanced
report and understands the need to identify and provide
additional, objective evidence of our performance improvements.
CP&L takes the observations, recommendations, and ratings of the
l'
SALP Board very seriously, and will continue to use them as an
input into our continuing process of evaluating and improving our
overall performance.
- As reflected by our comments during the November 9, 1989 meeting,
we generally concur with the SALP Board's observations.
The
following is a suggested clarification to the last paragraph of
Section I.A (page 2).
The second sentence would be accurate as
,
'
follows:
All nuclear activities, except Quality Assurance,
report to a single Senior Vice President - Nuclear.
L
The Senior Vice President - Nuclear and the Manager -
Quality Assurance report to an Executive Vjce
President.
/
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Document Control Deck
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NLS-89-311 / Page 2
,
..
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Steps have been, and are being taken, to address identified
concerns.
CP&L will continue to strive toward the. goals of
performance and operational excellence.
Yours very truly,
'
dN4'
Lynn W..
ry
PDM / pdm
(\\cor\\SALPRES)
cc:
Mr.
S. D. Ebneter
Mr. W. H. Ruland
Mr.
E.'G. Tourigny
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7
ENCLOSURE 3
ERRATA SHEETS FOR THE FINAL SALP REPORT
>
h
Line
Interim Report Reads
Final Report Reads
coversheet
2-
INTERIM SALP REPORT
FINAL SALP REPORT
,
1
42
November 12, 1989
November 12, 1988
v
2
32-36
All nuclear activities
All nuclear activities,
report
to....
except Quality Assurance,....
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$
ENCLOSURE
INTERIM SALP REPORT
U. S. NUCLEAR REGULATORY COMISSI
(NRC)
REGION II-
SYSTEMATIC ASSESSMENT OF LIC SEE PERFORMANCE
INSPECTION REPO
NUMBERS
-50-325/89-28 A
50-324/89-28
l.
CAROLINA POWER AN LIGHT COMPANY (CP&L)
BRU WICK'1 AND 2
.
SEPTEMBER
, 1988 - AUGUST 31, 1989
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I.
INTRODUCTION,
p
The Systematic Assessment of Licensee Performance (SALP) program s-an
integrated NRC staff effort to collect available observations an data on
a periodic basis and to evaluate licensee performance on the ba s of this
information.
The program is supplemental to normal regulator processes
used,to ensure compliance with NRC rules and regulations. - I is intended
to.be sufficiently diagnostic to provide a rational basis or allocation
of_ NRC resources and to provide meaningful feedback to
e licensee's
management regarding the NRC's assessment of their facil y's performance
'
in each functional area.
AN NRC SALP Board, composed of the staff members 1 ted below, met on
October 16,1989, to review the observations and d a on performance, and
to assess licensee performance in accordance wi h Chapter NRC-0516,
" Systematic Assessment of Licensee Performanc
The guidance and
"
evaluation criteria are summarized in Section
II of this report.
The
Board's findings and recommendations were fo arded to the NRC Regional
Administrator for approval and issuance.
This report is the NRC's assessment of t
licensee's safety performance
at. Brunswick Units 1 and 2 for the pe iod September 1,1988 through
August 31, 1989.
o
The SALP Board for Brunswick 1 and 2 was composed of:
L. A. Reyes, Director, Division o ' Reactor Projects (ORP),
Region II (RII) (Chairman)
K. E. Perkins, Acting Director Division of Reactor Safety, RII
W. E. Cline, Chief, Nuclear
erials Safety and Safeguards Branch,
Division of Radiation Saf y and Safeguards, RII
D. M. Verrelli, Chief, Rea or Projects Branch 1, DRP, RII
E. G. Adensam, Director,
oject Directorate II-1, Office of Nuclear
Reactor Regulation (N
)
W. H. Ruland, Senior Rp ident Inspector, Brunswick, DRP, RII
N. B. Le, Project Man ger, Project Directorate 11-1, NRR
Attendees at SALP
ard Meeting:
H. C. Dance, Chi f, Project Section 1A, DRP, RII
E.G.Tourigny/SeniorProjectManager,ProjectDirectorate11-1,NRR
T. Foley, Ope /, Project Engineer, Project Section IA, DRP, RII
R. E. Carroll
rations Engineer, Division of Licensee Performance and
Quality Evaluation, NRR
A.
Li
nsee Activities
he licensee operated Unit 1 with an availability factor of 51.4%.
The assessment period started with the unit in end-of-cycle coastdown
at 86.5% power.
The refueling outage, which was scheduled to begin
November 12, 1989, started a day early due to a turbine control
. . . . . . _ . _ _ _
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SEE ERRATA' SHEET
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ae
,
system initiated scram.
The outage . lasted 156 days, 86 days long
I
than planned.
Recirculation system piping weld overlays-and Appe dix
'
R modifications were the primary delay contributors.
Signifi
nt
,
valve and. motor operator maintenance and modifications were
150
' completed.
The unit now has 97% barrier fuel, eliminatin
any
preconditioning requirements during the current fuel c
le.
1
Followleg the refueling outage, Unit 1 -underwent normal power
l
operations except when it was taken off line for twent
days in
June 1989 to replace the reactor core isolation cooli
injection
i
valve and to replace the 1A core spray motor..
Unit 2 started the assessment period at 100% power nd ended at 83%,
'
end-of-cycle-coastdown to the September 1989 refue ing outage.
There
were two forced outages, both involving equipse
failure, with one
being complicated by personnel error. . Setpoin drift in a feedwater
>
control system inverter resulted in a scram,
eading to a three day
outage in November 1988.
A trip of both rec rculation pumps, due to
a loss of- the start-up auxiliary transform , required operators to
manually scram the reactor. This resulte in an eleven day outage in
- June 1989.
The-licensee operated the un t with a 96,1% availability
factor.
' The licensee completed several self-
sessments during the evaluation
,
period.
A third party consultan , Cresap, reviewed nuclear
operations at Brunswick and made
commendations to CP&L management.
-i
CP&L performed an Organization
Analysis which examined job
responsibilities and functions.
At the end of the assessment period,
the licensee eliminated cer in positions and changed their
organization based on the 0 ganizational Analysis recommendations.
The Corporate Management 0 rsight Team reviewed station operations
last period and made rec
endations that were implemented by the
,
plant this. assessment p iod.
Additionally, a major review of the
design of motor-operate valves was completed and documented.
Management changes w re made at the corporate and site level.
All
nuclear activities
eport to an Executive Vice President with all
three CP&L nuclea sites reporting to a single Senior Vice President.
Personnel reass nments included the maintenance manager, site
planning and c trol manager, training manager, and project manager
positions.
B.
Direct Ins ction and Review Activities
Besides
he routine inspections performed by the NRC staff, special
inspec ons were conducted as follows:
September 19-23, and October 3-5, 1988; ALARA team inspection to
evaluate effectiveness of actions to reduce collective dose and
assess managements awareness of, involvement in, and support of
Brunswick's program to keep radiation doses as low as reasonably
achievable (ALARA).
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