IR 05000397/1988045
| ML17285A273 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/13/1989 |
| From: | Bosted C, Johnson P, Sorensen R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17285A272 | List: |
| References | |
| 50-397-88-45, IEB-85-003, IEB-85-3, NUDOCS 8902280413 | |
| Download: ML17285A273 (9) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION REGION V
Report No:
Docket No:
Licensee:
Facility Name:
Inspection at:
50-397/88-45 50-397 Washington Public Power Supply System P. 0.
Box 968 Richland, WA 99352 Washington Nuclear Project No.
2 (WNP-2)
WNP-2 Site near Richland, Washington Approved by:
Summary:
Inspection Conducted:
December 12 - January 8, 1989 (/'
Inspectors:
~
/+~A~~
C. J.,Bosted, Senior Resident Inspector
~~
R.
C., Sorensen, Ress ent Inspector 0 nson, le Reactor" rojects Section
Date Signed
-/-/ =i Date Soigne
-'l~= /~-I ate agne Ins ection on December 12 - Januar 8,
1989 50-397/88-45 Areas Ins ected:
Routine inspection by the resident inspectors of control 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, 61726, 62703, 71707, 71710, 71714, 92701, 92702, 92720, and 93702 were covered.
Results:
No violations or deviations were identified.
An observed strength was the operation of the plant at full power for the report period without any significant problems.
An observed weakness, as discussed during the Management Meeting on January 5, 1989, was the number of entries by managers into the vital areas of the plant.
Three followup items were closed; no new items were opened.
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PDR ADQCK 05000397 PNU
DETAILS Persons Contacted L. Oxsen, Assistant Managing Director for Operations D. Bouchey, Director, Licensing and Assurance
- C. McGilton, Manager Safety and Assurance
- C. Powers, Plant Manager
+J. Baker, Assistant Plant Manager K. Cowan, Nuclear Safety Assurance Manager C. Edwards, Quality Control Manager
- R. Graybeal, Health Physics and Chemistry Manager
"J.
Harmon, Maintenance Manager
"A. Hosier, Licensing Manager D. Kobus, Quality Assurance Manager R. Koenigs, Technical Manager
- S. McKay, Operations Manager J. Peters, Administrative Manager W. Shaeffer, Assistant Operations Manager
- R. Webring, Assistant Maintenance Manager M. Wuestefeld, Assistant Technical Manager The inspectors also interviewed various control room operators, shift supervisors and shift managers, maintenance, engi'neering, quality assurance, and management personnel.
- Attended the Exit Meeting on January 6, 1989.
Plant Status At the start of the inspection period, the plant was operating at 80Ã power.
The plant reached lOOX power on December 14 and operated at that power level through the end of the reporting period.
On January 6; an increase in condensate conductivity was observed which required the plant to enter a chemistry procedure action level.
The plant was subsequently
.shut down on January 7 to repair condenser tube leaks.
Previousl Identified NRC Ins ection Items 92701 92702 The inspectors reviewed records, interviewed personnel, and inspected plant conditions relative to licensee actions on previously identified inspection findings:
a.
Closed Unresolved Item 397/87-19-08
Fire Threat to Shutdown Dsvsssons and s
Trans er Pum Rooms This issue involved a postulated diesel fuel line failure in a diesel generator (DG) room with a subsequent fire.
The fire sprinklers would actuate and could cause a burning fuel oil/water mixture to enter the common corridor outside from under the fire door and affect all three trains of DG cable The licensee responded by performing a calculation which showed that the drains were sized appropriately to be able to handle the flow from all 28 sprinklers in a
DG room actuating at the same time.
In addition, the licensee verified that all drains in all three DG rooms were unplugged.
Also, two modifications were implemented in each DG room as follows.
One installed curbs on the floor in front of the fire door leading into the corridor.
The other cut openings in the bottom of doors leading to the outside environment.
These modifications should preclude the occurrence of the type of scenario depicted above.
This item is closed.
b.
Closed Unresolved Item (397/87-19-16
Constraints on the Use of t e utomatsc De ressurszation S stem DS In >bit Switch This concern from the NRC's safety system functional inspection (SSFI) involved the use of the ADS inhibit switch.
Applicable WNP-2 emergency procedures had placed no constraints on its use.
The original intent of the ADS inhibit switch was to override ADS actuation during an anticipated transient without scram (ATWS) event when the ADS function would not be desirable.
However, no distinction was made in emergency procedures between ATWS events and loss-of-coolant accident (LOCA) events concerning the use of the inhibit switch.
The licensee revised applicable emergency procedures to specify the use o'f the ADS inhibit switch for ATWS events and the ADS 105-second timer reset button as needed for LOCA events.
This item is closed.
c ~
Closed Unresolved Item (397/87-19-34
Safet Parameter Dis la S stem SPDS Incons>stent wit Commitments This item involved a concern that the SPDS (also known as the Graphic Display System)
cathode ray'tubes (CRTs) were difficult to read from the Control Room Operator's desk, and even from in front of the control panels themselves.
The licensee replaced one worn out CRT and installed glare screens on both to make them more visible and readable.
This item is closed.
4.
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 Building Yard Area and Perimeter
.
b.
The following items were observed during the tours:
0 eratin Lo s and Records.
Records were reviewed against ec nica peci ication an administrative control procedure requirements.
Monitorin Instrumentation.
Process instruments were observed or corre ation etween c annels and for conformance with Technical Specification requirements.
(3)
(4)
(5)
(6)
(7)
Shift Mannin
.
Control room and shift manning were observed or conformance 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 verified to e in t e 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
een 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 indications o
system leakage, improper lubrica-tion, or other conditions that would prevent the system from fulfillingits functional requirements.
Annunciators were observed to ascertain their status and operability.
A periodic review of security records for the various managers'ccess into the plant's vital areas indicated that the number of visits was less than anticipated to ensure that management's policies and expectations were being addressed.
This concern was discussed with licensee management during the Management Meeting conduc-ted on January 5, 1989 (Meeting Report No. 50-397/89-05).
Fire Protection.
Fire fighting equipment and controls were observed for conformance with Technical Specifications and administrative procedure (8) Plant Chemistr
.
Chemical analyses and trend results were reviewe or conformance with Technical Specifications and administrative control procedures.
(9) Radiation Protection Controls.
The inspectors periodically observed radiological 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 personnel frisking practices.
Radiation monitoring equipment was frequently monitored to verify operability and adherence to calibration frequency.
(10) Plant Housekee in
.
Plant conditions and material/equipment storage were o served to determine the general state of cleanliness and housekeeping.
Housekeeping in the radiologi-cally controlled area was evaluated with respect to controlling the spread of surface and airborne contamination.
(11) ~Securit
.
The inspectors periodically observed security practices to ascertain that the licensee's implementation of the security plans was in accordance with site procedures, that the search equipment at the access control points was opera-tional, that the vital area portals were kept locked and alarmed, and that personnel allqwed access to the protected area were badged and monitored and the monitoring equipment was functional.
No violations or deviations were identified.
5.
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 required functions.
The inspectors also verified that the 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 operable.
Accessible portions of the following systems were walked down on the indicated dates.
~Sstem Diesel Generator Systems, Divisions 1, 2, and 3.
Dates December
Hydrogen Recombiners Low Pressure Coolant Injection, (LPCI)
Trains
"A"
"B", and
"C" 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 Water System 125V DC Electrical Distribution, Divisions I and
250V DC Electrical Distribution No violations or deviations were identified.
December 26, January
December 26, January
December 20, 26, January
December
December 26, January
December 26, January
December 28, January
December
December 21,
December 21,
6.
Surveillance Testin 61726 a.
Surveillance tests required to be performed by. the Technical Specifications (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 dispositioned.
b.
Portions.of the following surveillance tests were observed by the inspectors on the dates shown:
7.4.3.3.1.55 High Pressure Core Spray (HPCS) Level 8 Trip 7.4.3.7.1.8 Control Room Ventilation Rad Monitor Channel Functional Test (CFT)
Dates Performed December
December
7.4.5. 1.21 Automatic Oepressurization December
System Accumulator Backup Low Pressure Alarm CC No violations or deviations were identifie.
- Plant Maintenance 62703 During the inspection period, the inspectors observed and reviewed documentation associated with maintenance and problem investigation activities to verify compliance with regulatory requirements and with administrative and maintenance procedures, required gA/gC involvement, 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 activity:
Descri tion Date Performed 8.
Repair of MS-PCV-18A per AT 5892 January
No violations of NRC requirements or deviations were identified.
Cold Weather Pre arations 71714)
The inspector reviewed the licensee's procedure for implementing freeze protection, 1.3.37 - Cold Weather Operations.
In addition, the inspector accompanied the equipment operator responsible for verifying implemen-tation and adequacy of the various freeze protection measures during his rounds of the plant.
The inspector questioned the equipment operator on various aspects of the procedure and of the equipment log in which he recorded various data.
He appeared to be very knowledgeable concerning freeze protection measures.
The applicable procedure indicated that the operator should check room heating thermostats to verify proper settings at 70 degrees.
Although temperatures of the spaces visited appeared to be proper and heating units appeared to be functioning, the equipment operator's log did not contain provisions for documenting this verification.
This was
. discussed with plant management at the monthly exit meeting.
No violations or deviations were identified.
9.
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 appeared valid.
Within this scope, the following report was reviewed by the inspectors.
Monthly Operating Report for November 1988.
No violations or deviations were identifie.
Review of NRC Bulletin As requested by action item e. of Supplement 1 to NRC Bulletin 85-03,
"Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings,"
the licensee's letters dated May 13 and September 9,
1988 identified the additional valves to be addressed in
'their program in response to the original Bulletin.
Review of these responses by NRR indicated that the licensee's selection of the additional valves to be addressed in their program in response to the original bulletin meets the requirements of action item e. of the supplement to the Bulletin, and is acceptable.
11.
Exit Meetin (30703)
The inspectors met with licensee management representatives periodically during the report period to discuss inspection status, and an exit meeting was conducted with the indicated personnel (refer to paragraph I)
on January 6, 1989.
The scope of the inspection and the inspector's findings, as noted in this report, were discussed and acknowledged by the licensee representatives.
The licensee did not identify as proprietary any of the information reviewed by or discussed with the inspectors during the inspection.