IR 05000237/1988002
| ML17199U384 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/19/1988 |
| From: | Gardner R, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| 50-237-88-02, 50-237-88-2, 50-249-88-02, 50-249-88-2, GL-83-28, NUDOCS 8802250311 | |
| Download: ML17199U384 (10) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No:
50-237/88002(DRS); 50-249/88002(DRS)
Docket Nos:
50-237; 50-249 Licenses No:
DRP-19; DPR-25 Licensee:
Commonwealth Edison Company P. 0. Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Units 2 and 3 Inspection At:
Morris, Illinois Inspection Conducted:
January 12-28, Inspector: ~*{\\*~~~
J. H. Neisler
~\\\\*~
Approved By:
Ronald N. Gardner, Chief Plant Systems Section Inspection Summary 1988 Date Date Inspection on January 12-28, 1988 (Reports No. 237/88002(DRS);
No. 249/88002(DRS))
Areas Inspected:
Routine, announced inspection of the licensee's implementation of Generic Letter 83-28 in the areas of equipment classification, vendor interface, post maintenance testing and reactor trip system reliabilit The inspection also included a followup on previous inspection item Closed TI 2515/64Rl and TI 2515/9 (25564B, 92700)
Results:
No violations or deviations were identified.
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- DETAILS Persons Contacted Principle Licensee Employees E. Eenigenberg, Station Manager E. Netzel, QA Superintendent J. Acheterberg, Technical Staff Supervisor R. Geier, QC Supervisor
- E. Armstrong, Regulatory Assurance Supervisor
- R. Stols, Quality Assurance W. Betourne, Quality Assurance R. Meadows, Superintendent Maintenance D. Potts, Document Control Supervisor R. Dyer, Modification Group Leader
- J. R. Williams, Regulatory Assurance G. Wirth, Marter Mechanic, Mechanical Maintenance J. Williams, Electric Group Leader, Technical Staff R. Campbell, Instrument Maintenance F. Petrusich, Electrical Maintenance Staff G. Frankowich, Electrical Maintenance W. Wharry, Mechanical Maintenance J. Kovic, General Foreman, Substation construction B. Viehl, Project Engineer, Dresden BWR Engineering K. Knuston, Technical Staff
- C. Schroeder, Services Superintendent
- D. VanPelt, Assistant Superintende~t Maintenance
- Denotes those present at the exit intervie.
Licensee Action on Previously Identified Items (Closed) Violation (237/85032-03; 249/85028-03):
Failure to document the review and approval of test results for scram testing of single control rod drive hydraulic control unit The inspector reviewed procedure DTS-300-2 "Control Rod Drive Scram Testing and Scram Valve Timing Test" and OAP 9-3 "Procedure Review and Writing.
Both procedures have been changed to require review and acceptance of test results by the cognizant Technical Staff Enginee In addition, the reviews shall be performed against known acceptance criteria. This violation is close (Closed) Open Item (237/85032-02, 249/85028-02):
Tracking of General Electric service advise (SAL), service instruction (SIL) and technical instruction (TIL) letters recommended action The inspector reviewed the licensee's computerized tracking system and verified that tracking of the implantation of recommended actions for SAL's, SIL's, and TIL's was, being performe This item is closed.
- *
TI 2515/64Rl (Closed) and TI 2515/91 (Closed) Equipment Classification (1) This inspection area was previously addressed in inspection reports 50-237/85032 and 50-249/8502 During this inspection, the inspector selected five components in the reactor protection system and seven components in the core spray syste Review of the master equipment list (safety related component list) verified that each of the components was listed and properly classifie (2)
To determine the level of plant management oversight, the inspector reviewed procedures controlling the classification of structures, systems, components and parts; maintenance, modifications; procurement, storage and issue; inspection and testing of safety-related items; quality assurance procedures, audits and surveillances; and corporate level procedures for activities impacting safety-related structures, systems and component (3) The inspector reviewed SNED procedure Q12.l, "Classification and Listing of Safety-Related Structures Systems and Components,"
and QA procedures QP2-53, "Operations-Classification of Structures, Systems and components," and QP3-3, Classification of Systems, Components, Parts and Materials." These procedures provide direction for the performance of activities iffecting safety-related structures, systems and component (4) The inspector reviewed procedures for training and indoctrination of personnel performing activities affecting safety-related item Individual training and indoctrination records indicated that each individual had received the necessary training to qualify him to perform safety-related activitie (5) The inspector reviewed ten audit reports and eighteen surveillance reports documenting Quality Assurance audits and surveillances involving safety-related activitie The Quality Assurance organizations maintains a schedule of planned audits and surveillance for safety-related activities at the plan (6) The corrective action program for safety-related activities is described in the licensee's Quality Assurance Manua The inspector's review of corrective action for audit and surveillance findings revealed the corrective action for these findings was timely and adequat The Quality Assurance Department also schedules followup inspections of corrective actions after the action is complete and a finding is closed to determine if the corrective action was adequate to prevent a recurrence of the proble *
(7)
Review and evaluation of information concerning malfunctioning of equipment is controlled by the licensee's nonconformance (NCR) and Deviation Report (DR) program Both NCRs.and DRs are reviewed by management, quality assurance, and engineering, and when appropriate by the vendor or architect/engineer to determine the suitability of the equipment to perform its design functio (8)
The inspector reviewed three safty-related modifications on the core spray syste The modification packages, drawings, work requests, travelers and inspection reports were clearly identified as safty-related activitie No violations or deviations were identifie Vendor Interface This inspection area was addressed in inspection report 50-237/85032 and 50-249/8502 Observations during this inspection revealed that the licensee had not completed the implementation action of their vendor equipment technical information procedur This was also identified in the previous inspectio The licensee is participating in the Nuclear Utility Task Action Committee (NUTAC) and the Nuclear Plant Reliability Data System (NPRDS).
The inspector determined that procedures were in place to require periodic surveillances of vendors of safty-related components and service Procedures have been established for the reporting and evaluation of NPRDS and SEE-IN informatio No violations or deviations were identifie Post Maintenance Testing Post maintenance testing was addressed in inspection reports No. 50-237/85032 and No. 50-249/8502 Reactor Trip System Reliability At Dresden, on-line functional testing of the scram pilot solenoid valves is performed as reactor protection system instrument channel functional tests at the frequency required by the Technical Specification The inspector reviewed test procedures and test results for the following tests:
Reactor High Pressure Scram High Orywell Pressure Scram APRM Rod Block and Scram Low and Low-Low Water Level Trip
Main Steam Line Isolation Main Steam Line High Radiation Low Condenser Vacuum Scram Turbine Control Valve Fast Closure Mode Switch on Shutdown Scram RPS Electrical Protection Assemblies Procedures were adequate and test data sheets indicated that the testing was being accomplished at the frequencies required by the Technical Specification No violations or deviations were identifie.
Safety System Outage Modification Inspection (50-249/86009; 50-249/86012) followup (Closed) Deficiency 2.2-4 (249/86012-04):
Uncontrolled design changes for HGA relay replacemen The inspector confirmed that the licensee has revised procedure OAP 5.1 "Plant modification Program" to require the review of each modification to determine its impact on pending or related modification The purpose of this revision was to reduce or eliminate field notes or changes when more than one modification affects a component or syste OCR 86-59 was initiated to change drawing 12E 37570 to show the connections to be terminated on the correct termina This item is considered to be close (Closed) Deficiency 2.2-5 (249/86012-05):
Lack of change documentation for repair of EQ equipmen The licensee contracted with Bechtel Power Corporation to evaluate the acceptability of using Raychem WCSF-N heat shrinkable tubing to repair the motor lead insulation on the LPCI room coolers to maintain equipment environmental qualificatio The inspector reviewed Bechtel Chron-11286 that concluded that the Raychem tubing was acceptable for this application based on Wyle Laboratories Report 58722-This item is considered to be close (Closed) Observation 2.2-2 (249/86012-08):
Jumpers left in place with insufficient justification. The licensee has revised procedure OAP 7-4,
"Control of Jumpers and Lifted Leads," to require the shift control room engineer to perform a daily review of installed jumper In addition, the shift supervisor performs a monthly review and a field verification semi-annuall System engineers review justifications for jumpers that have been installed more than three months and prepare work requests for their removal or to make the temporary alteration permanen This item is considered to be close **
(Closed) Deficiency 2.4-5 (249/86012-26):
MMP not revised to be in accordance with Technical Specification The inspector verified that the licensee has reviewed and updated work packages to assure that the latest revision to procedure DFPP 4175-1 is in the work package *Procedures have been revised and work analysts instructed to log each revision of procedures to the appropriate work reques When a new procedure revision is issued the work analyst is required to review the log for outstanding work requests using that procedure and to assure that the revision is included in the work package The logging and review requirements have been expanded to include temporary procedure change This item is considered to be close (Closed) Deficiency 2.4-7 (249/86012-28):
Inadequate Substation Construction Department procedure The inspector reviewed the latest revisions of substation construction electrical installation procedure The procedures included safety related activities such as cable installation, termination, raceway installation, electrical equipment installation, installation of environmentally qualified conduit seals, and safety-related cable splicin Each procedure had been reviewed by Project Engineering, Sargent and Lundy, the on-site review committee and Quality Assuranc This item is considered to be close (Closed) Deficiency 2.5-1 (249/86012-38):
Installations not in accordance with work package The inspector reviewed Quality Control and Technical Staff reports verifying that the correct conductor had been terminated in the MCC The non safety cables in panels 2203-73A and 2203-738 have been installed in conduit as required by FCR #D426 Cable pull tensions have been evaluated by engineering, and since all cable was hand pulled and since the allowable tension exceeded 250 pounds, the evaluation determined the cable to be acceptable as installe Segregation code stickers have been added to conduit to assure 15 foot spacin The inspector reviewed completed FCR D-4283 relative to conduit support spacin NUTEC's evaluation of support spacing demonstrated that the conduit supports meet design criteria as installe The inspector verified that the ground clamps have been received and installe This item is considered to be close (Closed) Deficiency 2.5-2 (249/86012-39):
Electrical installation deficiency not correcte The inspector reviewed completed NCR 3159-01 The jumper has been removed and the field cable conductor reterminate This item is considered to be close (Closed) Open item 2.5-1 (249/86012-40):
Electrical cable to motor operated valve incorrectly identifie The cable marking was changed to 33825, the correct identificatio Bend radii was corrected during Inspection 8601 This item is considered to be closed.
(Closed) Deficiency 2.5-3 (249/86012-41):
Cable splice deficiencies.
The inspector verified that Raychem splices over installed cable braided jacket have been removed, the braid cut back and the splices replace The splices with short sleeves have been removed and replaced with splices installed with sleeves of a correct lengt The severe bend radii have been straightened, documented on a deviation report, inspected and evaluated and the splices on valves 3-1601-50A/B have been reworke (Closed) Deficiency 2.5-4 (249/86012-42):
LPCI/core spray relay wiring not per diagra The inspector verified that the wiring deficiencies identified by the team relative to the HGA relay replacement have been corrected, and that the modifications and functional testing were successfully complete This item is considered to be close (Close) Open Item 2.5-3 (249/86012-45):
0-ring replacement in EQ transmitter not documented in work packeag The 0-rings have been replaced in LT1526 and the licensee has implemented procedures to control the EQ progra The NRC EQ team reviewed transmitter seal replacement and did not identify seal replacement as being unacceptabl This item is considered to be close (Closed) Open Item 2.5-2 (249/86012-43):
Door relay markings not updated or controlle The inspector verified that the uncontrolled markings have been removed from cabinet 903-32 doo This item is considered to be close (Closed) Deficiency 2.5-5 (249/86012-44):
Installation discrepancies for LPCI room cooler motor replacemen Motor lead splices have been reworke Bechtel evaluation determined that WSCF tubing was an acceptable replacement for Scotch tap The inspector verified that one pulley belt was replaced and both were properly adjuste The flexible conduit was inspected, tightened and left in place in accordance with WR D5377 This item is considered to be close (Closed) Unresolved Item 2.5-3 (249/86012-54):
Concerns with Unit 3 pump room sprinkler syste The inspector reviewed inspection documentation rework requests and engineering evaluations of the piping installed under FCR 460 The deficiencies were corrected or resolved by engineering evaluations with the loose hanger correcte The licensee's inspection contractor performed walkdown and QA audits to assure the system met the design criteria. The installation contractor has been removed from the CECo approved bidders list. This item is considered to be close (Closed) Deficiency 4.1-1 (249/86009-12):
Separation criteria for reactor vessel level instrumentatio The inspector reviewed the licensee's evaluation of the redundant channel separation, SL 4413, and Power Supply Analysis of ATS Power Supplies and Impacted Equipment, SL 4413, Appendix As a result of these evaluations, the licensee has retrained cables, relocated relays and installed metal jackets on certain cables to achieve adequate separatio The licensee's evaluations included hot shorts, scram logic, single failure criterion and Appendix R requirement The inspector verified that separation modifications and drawing corrections determined to be necessary by the evaluations had been complete This item is close **
(Closed) Deficiency 4.1-2 (249/86009-13):
Reliability, failure modes and response time requirement for certain modification The inspector reviewed the safety analysis performed subsequent to the SSOM The analysis included reliability, failure modes and response tim Measured response time for the analog unit was 0.508 seconds compared to 1.0 seconds for the originally installed Yarway switc The deviations from the General Electric Topical Report NED0-21617A recommendations resulted from the necessity to use environmentally qualified (EQ)
transmitter The GE recommended Rosemount 1151 transmitters were not EQ, therfore, they were not suitable for this applicatio Instead, the licensee used Rosemount 1153 transmitters which have the same electronic, reliability and time characteristics as the non-EQ 1151 transmitter This item is considered to be close (Closed) Unresolved Item 4.1-3 (249/86009-14):
Selection of interruptible power sources for analog transmitter replacement modification The inspector reviewed the licensee's reevaluation of the interruptible power sources in SL4413, supplement 1, dated July 31, 198 The evaluation concluded that the addition of power supplies had not degraded the safety functions of the protection and safeguards system An additional 10 CFR 50.59 review of the modification concluded that the analog trip system improved reliability when compared to the non-qualified mechanical trip switche This item is considered to be close (Closed) Unresolved Item 4.1-4 (249/86009-15):
High and low pressure coolant injection (HPCI and LPCI) system dependency on neutron monitoring system battery sources for analog transmitter replacemen The inspector reviewed the additional 10 CFR 50.59 review for the modificatio The review confirmed that the 24/48 voe battery reliability was equivalent to the 125 VDC reliabilit The 24/48 VDC batteries are Class lE electrical equipment with a qualified life of ten years and the licensee has a battery replacement program based on the ten-year qualified lif The inspector also reviewed Sargent and Lundy Report SL-4413 that confirmed the batteries' suitability as a power source for the analog transmitter This item is considered to be close (Closed) Unresolved Item (249/86009-16):
Environmental qualification documentation for analog transmitter replacement modificatio The inspector reviewed Amerace Corporation Test Report ES-2000, Revision The Agastat relay allowable contact bounce is 10-millisecond The Agastats were tested at their operating voltage of 125 VDC at Amerace, separate from the Nutherm test of the Rosemount transmitters within the cabinet The licensee has reviewed th~ acceptance criteria in the Nutherm EQ procedure and determined that the two millisecond criteria for contact bounce compared to the allowable 10 milliseconds for the Agastats and the 100-200 millisecond drop out time for the reactor protection system HFA relays is acceptable for this particular trip channe The cabinets are not located in a harsh environment so the environmental concerns are seismic qualification with negligible temperature, humidity or radiation impact This item is considered to be closed.
(Closed) Deficien-cy 4.4-1 (249/86009-22):
Reactor water clean-up room leak detection system safety-related and non-safety related circuit Isolatio The inspector reviewed the licensee's breaker coordination study that confirmed the adequacy of the Class lE connections to non Class lE load Review of the modification and plant drawings confirmed that no new breakers were added during the modificatio This item is considered to be close (Closed) Deficiency 5.1-1 (249/86009-24):
250 volt battery sizing repor The inspector reviewed calculation 7056-00-19-10 that used plant specific motor dat The calculation using specific motor data provided a less conservative load cycle on the battery than the National Electric Code (NEC) based calculatio Motor starting current, when used, proved to be less conservative than the NEC values used in the original calculatio The inspector reviewed modification 12-3-84-121 to modify the battery room HVAC to maintain battery room temperature between 70°F and 80° The modification was completed in March 198 This item is considered to be close (Closed) Deficiency 5.1-2 (249/86009-25):
125 volt battery cell selectio The inspector reviewed the approved version of calculation 756-00-19-The calculation confirmed that the battery cells were adequately designe The calculation used a minimum temperature of 70°F based on the implementation of modification 12-3-84-121 to the battery room HVAC syste This item is considered to be close (Closed) Observation 5.1-3 (249/86009~26): 125 volt Battery Sizing Calculatio The inspector reviewed calculation 7056-11-19-5 Revision 1, dated January 18, 198 The calculation included 480 volt buses 20 and 3 The Sargent and Lundy methodology contains the explanation and justification for using the 2/3 diversit The load for the generator/transformer backup relay panel was included in the calculation as circuit #7 of DC reserve bus 28~2. The normal load for the HPCI control panel was included in the calculation in 125 VDC bus 2A-No inconsistancy was observed in the number of loads tripping and closing on 480 bus 2 This item is considered to be close (Closed) Deficiency 5.1-4 (249/86009-27):
Unit 1 HPCI battery tie voltage drop calculatio The inspector reviewed calculation 7175-30-19-1, Revision 0, and Revision 1; and calculation 7046-00-19-5, Revision Calculation 7046-00-19-5, Revision l confirmed a load increase of approximately 55 ampere This increase was considered in calculation 7175-30-19-1, Revision 1 and confirmed that the bus voltage can be maintained above the 105VDC design for two hours without load sheddin With load shedding required by plant procedure DGA-13, the 105 VDC can be maintained for over four hour This item is considered to be close (Closed) Deficiency 5.1-5 (249/86009-28):
Errors in updated documentation for 24/48 vo 1 t batterie The *inspector reviewed drawing 12E-3324, Revision M, June 30, 198 Thi~ drawing revision shows the 24/48 volt batteries to be 190 ampere-hour rate The UFSAR has been changed to 190 ampere-hour This item is considered to be close *g (Closed) Deficiency 5.2-1 (249/86009-32):
Documentation lacking for cable selectio The licensee did not properly document the voltage dro However, subsequent to the inspection, the licensee performed a verification test to confirm system operability and to measure the cable voltage dro Bechtel review, Chron 10988 confirmed the voltage to be adequate to operate the equipment in the cabinet This item is considered to be close Exit Interview The inspector met with licensee representatives at the conclusion of the inspection and summarized the scope and findings of the inspectio The licensee acknowledged the inspector's comment The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed during the inspectio The licensee did not identify any such documents or processes as proprietar