IR 05000397/1990003
| ML17285B187 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/02/1990 |
| From: | Johnson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17285B185 | List: |
| References | |
| 50-397-90-03, 50-397-90-3, NUDOCS 9004200548 | |
| Download: ML17285B187 (12) | |
Text
Report No:
Docket No:
Licensee:
U.S
'NUCLEAR REGUL'ATORY COMNISS ION REGION V
50-397/90-03 50-397 Washington Public Power Supply System P. 0.
Box 968 Rich'land, WA 99352 Facility.'Name:
.
Pashington Nuclear Project No.
2 (MNP-2)
Inspection at:
MNP-2 Site near Richland, Mashington Inspection Conducted:
January 29 - Narch 4, 1990 Inspectors:
C. J. Bosted, Senior Resident Inspector R.
C. Sorensen, Resident Inspector Approved by:
P..
hnson, hief Reacto Projects Section
'Ro Da e Signed Summary:
Inspection on January 29 - March 4, 1990 (50-397/90-03)
~AI d:
R t
t d
t by R
td t
y t room operations, licensee action on previous inspection findings, engineered safety feature (ESF) status, surveillance program, maintenance program, licensee event reports, special inspection topics, procedural adherence, and review of periodic reports.
During this inspection, Inspection Procedures 30703, 60705, 61726, 62703, 75707, 71710, 90712, 90713, 92700, 92701, 92702 and 255104 were utilized.
Safet Issues Mana ement S stem (SINS Items:
None.
Results:
Si nificant Safet Matters:
None.
Summar of Violations and Deviations:
No violations were identified.
0 en Items Summar
Four Part 21 followup items were closed:
one new inspector followup item was opened.
9004200548 900403 PDR ADOCN, 05000397
PNU
DETA1LS 1.
Persons Contacted
- C. Powers, 'Plant Manager
- D Kobus, guality Assurance Manager
- J.. Baker, Assistamt:Plant Manager
- A. Hosier, Licensing Manager C. Edwards, guality Control Manager R. Graybeal, Health Physics and Chemistry Manager J.
Harmon; Maintenance Manager R. Koenigs, Techni,cal Manager S. McKay, Operations Manager
- J. Peters, Administrative Manager
- G. Gelhaus, Assistant Technical. Manager
- R. Conserriere, Acting Assistant Operations Manager
- R. Webring, Assistant Maintenance Manager The inspectors:also interviewed various control room operators, shift supervisors and shift managers, maintenance, engineering, quality assurance, and management personnel.
- Attended the Exit Meeting on March 7, 1990.
2.
Plant Status At the start of the inspection period, the plant was operating at 100%.
The plant continued to operate at that power level throughout the reporting period.
3.
0 erational Safet Verification 71707 a.
Plant Tours The following plant areas were toured by the inspectors during the course of the inspection:
Reactor Building Control Room Diesel Generator Building Radwaste Building Service Water Buildings Technical Support Center Turbine Generator Buildinq Yard Area and Perimeter b.
The following items were observed during the tours:
(1)
0 eratin Logs and Records.
Records were reviewed against Tec nical Specification and administrative control procedure requirement (4)
(5)
{e)
(s)
(g)
(io)
'Yonitorin Instrumentation.
Process instruments were observed or corre at~on etween c annels and for conformance with Technical Specification requirements.
Shift llannin.
Control room and shift manning were observed for con ormance with 10 CFR 50.54. (k), Technical Specifica-tions, and administrative procedures.
The attentiveness of the operators was observed in the execution of their duties, and the control room was observed to be free of distractions such as non-work related radios and reading materials.
E ui ment Lineu s.
Valves and electrical breakers were veri ied to e in the position or condition required by Technical Specifications and administrative procedures for the applicable plant mode.
This verification included routine control board indication reviews and conduct of partial system lineups.
Technical Specification limiting conditions for operation were verified by direct observation.
E ui ment Ta in
.
Selected equipment, for which tagging requests a
been initiated, was observed to verify that tags were in place and the equipment was in the condition specified.
General Plant E ui ment Conditions.
Plant equipment was o serve or in ications o
system leakage, improper lubri-cation, or other conditions that would prevent the system from fulfillingits functional requirements.
Annunciators were observed to ascertain their status and operability.
Fire Protection.
Fire fighting equipment and controls were observed for conformance with Technical Specifications and administrative procedures.
~Pi Ch i
.
Ch i
iy d
d reviewed for conformance with Technical Specifications and administrative control procedures.
Radiation Protection Controls.
The inspectors periodically o serve ra io ogica protection practices to determine whether the licensee's program was being implemented in conformance with facility policies and procedures and in compliance with regulatory requirements.
The inspectors also observed compliance with Radiation Exposure Permits, proper wearing of protective equipment and personnel monitoring devices, and adherence to personnel frisking practices.
Radiation monitoring equipment was frequently monitored to verify operability and adherence to calibration frequency.
Plant Housekee in
. Plant conditions and material/equipment storage were o served to determine the general state of clean-liness and housekeeping.
Housekeeping in the radiologically
controlled area was evaluated with respect.to controlling the
.spread of surface and airborne contamination.
On three occasions, during tours of the radiologically controlled area (RCA), the inspector observed evidence of eating, drinking and smoking within within the RCA.
Candy wrappers, cigarette butts, and a beverage can were found in the.Division 2 diesel generator equipment room.
Used chewing gum, candy wrappers and sunflower seed hulls were found in the main passageway between the reactor building and the diesel generator building.
Candy wrappers were also found in the stairwell going to the cable routing room in the radwaste building.
The inspector did not observe anyone'onsuming these articles.
Licensee management was informed each time these items were discovered.
Management took steps to increase personnel awareness that these activities are prohibited within the RCA.
Signs were painted on the entrance doors to the RCA to inform those who enter that eating, drinking, and smoking are prohibited.
Each work center manager reissued standing. orders expressing management's expectations regarding this issue.
The site general employee training was also modified to increase the emphasis on this issue to the plant personnel receiving annual site access retraining.
This item will be followed up in a future inspection to evaluate the effectiveness of the plant management's efforts to stop this practice (Followup Item 397/90-03-01).
(11) ~Securit
.
The inspectors periodically observed security practices to ascertain that the licensee's implementation of the security plan was in accordance with site procedures, that the search equipment at the access control points was operational, that the vital area portals were kept locked and alarmed, and that personnel allowed access to the protected area were badged and monitored and the monitoring equipment
. was functional.
No violations or deviations were identified.
4.
En ineered Safet Feature S stem Walkdown (71707, 71710 Selected engineered safety feature systems (and systems important to safety)
were walked down by the inspectors to confirm that the systems were aligned in accordance with plant procedures.
During the walkdown of the systems, items such as hangers, supports, electrical power supplies, cabinets, and cables were inspected to determine that they were operable and in a condition to perform their r equired functions.
The inspectors also verified that system valves were in the required position and locked as appropriate.
The local and remote position indication and controls were also confirmed to be in the required position and operabl Accessible port'ions-of the following systems were walked down on the indicated dates.
~Sstem Diesel "Generator (DG) Systems,
- Divisions.1, 2,.and 3.
Hydrogen Recombiners
'Low Pressure Coolant Injection, (LPCI)
Trains "A"
"8" and
"C" Dates February 22,
February
February
Low Pressure Core Spray (LPCS)
High Pressure Core Spray (HPCS)
Reactor Core Isolation Cooling (RCIC)
Scram Discharge Volume System Standby Liquid Control (SLC) System Standby Service Mater System 125V DC Electrical Distribution, Divisions 1 and
250V DC Electrical Distribution No violations or deviations were identified.
February
February
February
February 5,
February
February
February
February
5.
Surveillance Testin 61726 Portions of the following surveillance tests were observed by the inspectors on the dates shown:
~0 7.4.3.1.1.6 Reactor pressure vessel January
(RPV) High Pressure Scram Channels A 8 C Channel Check (CC)
Procedure Surveillance tests required to be performed by the Technical Specifica-tions (TS) were reviewed on a sampling basis to verify that:
(1) the surveillance tests were correctly included on the facility schedule; (2)
a technically adequate procedure existed for performance of the surveillance tests; (3) the surveillance tests had been performed at the frequency specified in the TS; and (4) test results satisfied acceptance criteria or were properly dispositione :4.'3'. 1.1 '53 7 4.3.6.2'1'PV
.High Pressure Scram Channels
.B
&
D CC Recirculation Flow C
Rod Block Channel Functicnal Test (CFT)
- .February
- February
7.4.3. 1.1 49 Average Power Range Monitor February
(APRN) Core Thermal Power CC 7.4.5. 1.21 Automatic Depressurization System Backup Low Pressure Alarm Test 7.4.8.1.1 2. 12 High Pressure Core Spray DG Nonthly Operability Test February
February
7.4.7.9.
Weekly Bypass Valve Testing March
7.4. 1.3.1.2 Weekly Control Rod Exercise March
No violations or deviations were identified.
6.
Plant Maintenance (62703)
During the inspection period, th'e inspectors observed and reviewed documentation associated with maintenance and problem investigation activities to verify compliance with regulatory requirements, adherence to administrative and maintenance procedures, required QA/QC involve-ment, proper use of safety tags, proper equipment alignment and use of jumpers, personnel qualifications, and proper retesting.
The inspectors verified that reportability for these activities was correct.
The inspectors witnessed portions of the following maintenance activities:
Descri tion Dates Performed Repair Control Rod Drive (CRD)
February
Temperature Recorder TR-18 per AS 4326 Repair Heater Drain Tank HD-TK-2D Temperature Element per AS 3569 Install fire seals for CRD rebuild room HVAC per AS 3676 ho violations or deviations were identified.
February
February
7..
Part
Re orts (90712, 92701)
a.
Closed)
89-16-P, Limiiorque Yalve Operator Housing Cover Defect During motor operator valve (MOV) testing, a defect was discovered in the upper housing cover of the reactor core isolatio'n cooling (RCIC) valve Y-63 motor operator.
Test failures led to examination.
of the MOV.
Excess material was discovered on the inside of the cover which remained from the casting process.
This excess material caused the upper housing cover to bear on the drive sleeve of the upper thrust bearing, preventing its free rotation.
This would cause the MOV to produce insufficient stem thrust, which could cause the valve to fail to operate.
'The upper housing cover was machined to proper clearances.,
Limitorque was notified of the defect to assess its generic implications.
Other similar valves have been previously inspected by the licensee and no similar defects were identified.
This item is closed.
b.
(Closed) 89-18-P, ASEA Brown Boveri (ABB) Current Transformer
~pi1S ig Current transformers (CTs) are normally encapsulated in an epoxy compound.
The epoxy used in some CTs supplied by ABB was found to be softening, which would eventually lead to the failure of the CT.
High humidity environments in the presence of elevated ambient temperatures were found to have a snftening effect on the epoxy hardener.
ABB recommended that CTs be inspected every 18 months for degrada-tion of the epoxy encapsulant material.
This can be performed by pressing a fingernail or other hard object into the material, with the CT deenergized, and checking for deformation and tackiness.
From discussions with licensee representatives, the inspector understood that WNP-2 uses approximately 100 CTs supplied by ABB, mainly in ground fault detection.
The licensee revised PPM 10.25.101,
"Testing and Setting of Type GR/GRC Ground Fault Relays," to check for encapsulant hardness while performing other preventive maintenance (PM) tasks on these CTs.
This PM is performed every 24 months, which was justified by the licensee based on the relative low humidity and mild climate which prevails at WNP-2.
The licensee representative stated that approximately
CTs have been examined to date, and all were found to satisfactory.
This item is close (Closed) 89-21-P, Target:Rock Relay Kit's With Failed Solder Ooints Target Rock Coi poration supplied the licensee"with" 17,relays used for position indication circuitry on solenoid operated valves.
These were to be, used for replacing components on certain valves to meet environmental qualification'equirements.
These relay kits were fabricated especially for the Supply System.
During installation in the field, they were observed to have the followirg-defects; Cold solder condition Insufficient solder joints Failed solder joints The kits were returned to Target Rock where they were reworked and later successfully installed in the applicable valves.
The licensee reported the condition under the requirements of 10 CFR
to both the NRC and Target Rock.
Target Rock was placed on the licensee's restricted use list for procurement, which meant that certain actions will be taken prior to purchasing their parts or equipment.
Also, training was held with receiving inspectors on how to inspect for properly. soldered joints, since this defect was not discovered during the receipt inspection process.
Finally, Target Rock committed to the licensee to complete certain corrective actions deemed appropriate as a result of this, problem, including:
Ensuring that relay assemblies are soldered by qualified personnel using qualified procedures.
Development of a soldering procedure to prevent any further occurrence of cold soldered joints.
Documentation of inspection criteria for soldered connections.
This item is closed.
Closed 89-25-P, Potential Defect in Limitorque SNB-00 and SMB-000 ype Torque Switches This Part 21 notification from the Limitorque Corporation involved a defect identified at two other nuclear facilities.
Torque switch failure occurred in Limitorque motor operators as a result of stationary contact screws becoming loose.
These screws have fiber spacers, and position the torque switches.
When the screws loosen, the torque switch setting changes, or the torque switch becomes altogether inoperable.
These failures are limited to torque switches manufactured prior to 1981 for SNB-000 type motor operators, and prior to 1976 for
'MB-00.
MNP-2 has approximately 89 SNB-00 hand SNB-OGO safety-related motor.operators installed.
Sixty-eight'of the 89 suspect torque switches 'had.already been replaced Sor other.
reasons.
As the result of a similar concern identi'fied previously,'the licensee had revised PPM 10.25.4 "Inspection of Motor Operated Valves and Controls," to inspect torque switches for loose con.act screws and to replace fiber shims if loosening is observed.
This PM is performed on a biannual basis.
Limitorque now recommends that toroue switches with fiber spacers be replaced.
By April 10, 1990, the licensee plans to revise PPM 10.25.4 to replace any torque switch in a safety-related application found with fiber spacers.
The -replacement of %he
remaining affected torque switches that are in the drywell or steam tunnel will be performed during the 1990 refueling outage, scheduled to begin on April 20.
This item is closed, 8.
Fitness for Dut Trainin 255104)
Certain of the licensee's Fitness for Duty training classes were observed by the inspector to determine whether the requirements of
CFR 26 were being implemented.
At least one session nf training was to be observed for personnel with unescorted access, personnel providing site escort duties, and for supervisors of activities covered by the rule.
Specific training requirements were delineated in 10 CFR 26 for escorts and supervisors.
The inspector observed training for unescorted site access and escorts on February 8 and 15 and for all groups on March 1.
The site access training and escort training were conducted together and the supervisor training was conducted subsequent to the general site access/escort training.
The licensee utilized a lecture method with a supplemental videotape.
The inspector observed an improvement in the training efforts during the three presentations of the site access/escort sessions.
The inspector commented to the site personnel relations manager that the program was weak in the use of visual aids to assist the trainees in recognizing contraband drugs and where they could be concealed.
For the March I class, a handout was given to the class that listed the locations where local law enforcement departments have been finding illegal drugs hidden on their "suspects".
Licensee management told the inspector that they will continue to obtain information from local law enforcement agencies to upgrade their fitness for duty training.
No violations or deviations were identifie II Observation of Fuel Recei t:and Its ection (60705)
I The inspector observed portions of %he sequence f'r fuel receipt and inspection from arrival onsite to final placement in the fuel pool,.
Special emphasis was placed on the upending portion of the sequence as problems had been experienced in this area in the past. 'adiation monitoring instruments were.checked to ensure that they were in current calibration and had been.source checked.
The licensee person in charge of the evolution provided good direction and leadership, and displayed a
sense of overall responsibility.
Two procedures were reviewed for adequacv and proper approval and tc ensure that they were being followed.
Plant Procedures Manual (PPYi)
6.2.1,
"Receipt of New Fuel and Shipping Truck to Bay Activities," and PPN 6.2.2,
"New Fuel Handling, Railroad Bay to Refuel Floor Activities,"
were reviewed.
Procedure enhancements had been implemented since last year to provide even more specific guidance in some of these activities.
Receipt of new fuel was ongoing at the end of the inspection period.
Inspection of these activities will continue during the next inspection period.
No violations or deviations were identified.
"
Review of Periodic and S ecial Re orts 90713 Periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9.1 and 6.9.2 were reviewed by the inspector.
This review included the following considerations:
the report contained the information required to be reported by NRC requirements; test results and/or supporting information were consistent with design predictions and performance specifications; and the reported information was valid. Within the scope of the above, the following reports were reviewed by the inspectors.
tionthly Operating Report for January 1990.
Semiannual Effluent Report for July 1 - December 31, 1989.
No violations or deviations were identified.
Exit Heetin 30703 The inspectors met with licensee management representatives periodically during the report period to discuss inspection status.
An exit meeting was conducted with the indicated personnel (refer to paragraph 1) on Narch 7, 1990.
The scope of the inspection and the inspectors'indings, as noted in this report, were discussed with and acknowledged by the licensee representatives.
The licensee did not identify as proprietary any of the information reviewed by or discussed with the inspector during the inspection.