IR 05000528/1987043
| ML17300B199 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/28/1988 |
| From: | Ball J, Fiorelli G, Richards S, Sorensen C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17300B198 | List: |
| References | |
| 50-528-87-43, 50-529-87-42, 50-530-87-45, NUDOCS 8802170252 | |
| Download: ML17300B199 (16) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos:
Docket Nos:
License Nos:
Licensee:
50-528/87-43, 50-529/87-42, 50"530/87-45 50-528, 50-529, 50-530 NPF"41, NPF-51, NPF-74 Arizona Nuclear Power Project P.
0.
Box 52034 Phoenix, AZ. 85072-2034 Ins ection Conducted:
December 6, 1987, through January 16, 1988.
Inspectors:
J.
1, Residen nspector
/ 4$
'at Si ned G.
F i, Resident spector te igned C.
Sor s
, Project spector D
e gned Approved By:
S.
Ric
, Chief, E
ineering ction ate igned Summary:
Ins ection on December
1987 throu h Januar
1988 Re ot t Nos.
50-528/87-43 50-529/87-42 and 50-530/87-45
.
Areas Ins ected:
Routine, onsite, regular and backshift inspection by the two resident inspectors and one regional based inspector.
Areas inspected included:
review of plant activities, plant tours; engineered safety feature system walkdowns; surveillance testing; plant maintenance; verification of containment integrity; containment local leak rate testing; maintenance program implementation; design changes and temporary modifications; licensed operator training; followup licensee event reports; and review of periodic and special reports.
During this inspection the following Inspection Procedures were covered:
37700, 41701, 61715, 61720, 61726, 62726.
62700, 62703, 71707, 71707-1,71709, 71710, 72302, 72580, 72701, 93702.
Results:
Of the areas inspected, no violations of NRC requirements or deviations were identified.
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@gal gDOCH, pDP
DETAILS 1.
Persons Contacted:
The below listed technical and supervisory personnel were among those contacted:
Arizona Nuclear Power Pro ect ANPP)
- J. Allen, Plant Manager, Unit 1 L. Brown, Manager, Radiation Protection and Chemistry
- F. Buckingham, Operations Manager, Unit 2
- R. Butler, Director, Standards and Technical Support B. Cederquist, Manager, Chemical Services W. Fernow, Manager, Training R.
Gouge, Operations Manager, Unit 3 J.
G. Haynes, Vice President, Nuclear Production W. E. Ide, Plant Manager, Unit 2 J. Kirby, Director, Site Services R. Papworth, Director, guality Assurance G. Perkins, Manager, Central Radiation Protection
- T. Schriver, Manager, Compliance G. Sowers, Manager, Engineering Evaluations
- E. E.
Van Brunt, Jr., Executive Vice President J.
Vorees, Manager, Nuclear Safety R. Younger, Operations Manager, Unit
0. Zeringue, Plant Manager, Unit 3 The inspectors also talked with other licensee and contractor personnel during the course of the inspection.
"Attended the Exit Meeting on January 21, 1988.
2.
Review of Plant Activities a.
Unit
Unit 1 continued the first cycle refueling outage throughout this inspection period.
Major activities included completion of reactor coolant pump seal replacement and shaft replacement/
repair, integrated safeguards testing, and the fill and venting of the reactor coolant system.
On January 8, the unit entered Mode 4.
During the subsequent heatup and pressurization of the reactor coolant system, excessive leaking was noted to be occurring from the seals of 2 of the 4 reactor coolant pumps.
The unit was returned to Node 5 on January 9 to evaluate the leakage problem.
The unit remained in Node 5 at the end of the inspection period.
b.
Unit 2 Unit 2 operated essentially at 100K throughout the perio c.
Unit 3 Power ascension testing continued in Unit 3 throughout this inspection period.
On December 6, the unit was restarted after having conducted a shutdown from outside the control room test.
On December 17, while operating at 50 percent power, the unit experienced a reactor trip due to misalignment of 2 groups of part length control rods.
The control rods became misaligned due to the failure of a logic card in the rod drive mechanism sequence while performing testing involving movement of the control rods.
Following an evaluation and replacement of the failed logic card, the unit was restarted on December 19.
On December 29, while escalating power from 90 to 95 percent, the unit experienced a turbine generator trip due to an erroneous high stator cooling wate~ temperature indication.
At the time of the turbine trip, the reactor cutback system was inservice such that reactor power was automatically reduced to 30 percent.
After actions were completed to correct the problem with the stator cooling temperature sensor problem, the unit was resynchronized to the grid on December 30, 1987.
On January 1, 1988, the unit was operated at 100 percent for the first time.
By January 7, 1987, testing at the 100 percent plateau was completed.
The unit remained at full power through the end of the inspection period.
d.
Pl ant Tours The following plant areas at Units 1, 2 and 3 were toured by the inspector during the course of the inspection:
Auxiliary Building Containment Building Control Complex Building Diesel Generator Building Radwaste Building Technical Support Center Turbine Building Yard Area and Perimeter The following areas were observed during the tours:
1.
0 eratin Lo s and Records Records were reviewed against Technical Specification and administrative control pro-cedure requirements.
2.
Monitorin Instrumentation Process instruments were observed for correlation between channels and for con-formance with Technical Specification requirements.
observed for conformance with 10 CFR 50.54.(k), Technical Specifications, and administrative procedure.
E ui ment Lineu s Valve and electrical breakers were verified to be 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.
E ui ment Ta in Selected equipment, for which tagging requests had been initiated, was observed to verify that tags were in place and the equipment in the condition specified.
General Plant E ui ment Conditions Plant equipment was observed for indications of system leakage, improper lubrication, or other conditions that would prevent the system from fulfillingtheir functional requirements.
Fire Protection Fire fighting equipment and controls were observed for conformance with Technical Specifications and administrative procedures.
8.
for conformance with Technical Specifications and admin-istrative control procedures.
~Secorit Activities observed for conformance with regulatory requirements, implementation of the site security plan, and administrative procedures included vehicle and personnel access, and protected and vital area integrity.
Plant Housekee in Plant conditions and material/
equipment storage were observed to determine the general state of cleanliness and housekeeping.
Housekeeping in the radiologically controlled area was evaluated with respect to controlling the spread of surface and airborne contamination.
Radiation Protection Controls Areas observed included control point operation, records of licensee's surveys within the radiological controlled areas, posting of radiation and high radiation areas, compliance with Radiation Exposure Permits, personnel monitoring devices being properly worn, and personnel frisking practices.
No violations of NRC requirements or deviations were identified.
3.
En ineered Safet Feature S stem Malkdowns - Units 1 2 and
Selected engineered safety feature systems (and systems important to safety)
were walked down by the inspector to confirm that the systems were aligned in accordance with plant procedures.
During the walkdown of the systems, items such as hangers, supports, electrical cabinets, and cables were inspected to determine that
they were operable, and in a condition to perform their required functions.
Unit 1 Accessible portions of the following systems were walked down on the indicated date:
~Ss tern Shutdown Cooling Operation, Train "A" Date 01-04-88 Emergency Diesel Generator System, Train "B" 12-15-87 Unit 2 Accessible portions of the following systems were walked down on the indicated dates:
~Sstem Emergency Diesel Generator System, Trains "A" and "8" Date 12-21-87 Class lE Battery Supply Channel
"B" Unit 3 01-04"88 Accessible portions of the following systems were walked down on the indicated dates:
~Sstem High Pressure Safety Injection System, Trains "A" and "B" Date 01-04-88 Low Pressure Safety Injection, Trains "A" and "B" 01-04-88 No violations of NRC requirements or deviations were identified.
4.
Surveillance Testin
- Units 1 2 and
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 dispositione b.
Portions of the following surveillances were observed by the inspector on the dates shown:
Unit 1 Procedure Descri tion Dates Performed 73ST-9CL07 Local Leak Rate Test of Containment Vent Purge Isolation Valves.
12-16-87 73ST-9HJ01 Control Room Air Filtration 12-18-87 Unit Air Fl ow Capacity and Pressurization Test.
36ST-1SB02 PPS Bistable Trip Functional 12-22-87 Test.
36ST-9SB04 PPS Functional Test-PPS/ESFAS Logic.
01-04-88 Unit 2 Procedure Descri tion Dates Performed 36ST-9SB02 PPS Bistable Trip-Functional Test 12-21-87 42ST-2EC03 Essential Chilled Water System Inoperabl e Surveillance 01-05-88 Unit 3 73ST-3ZCOl Tendon Integrity.
43ST-3RC02 RCS Water Inventory Balance.
Dates Performed 12-14-87 12-30-87 No violations of NRC requirements or deviations were identified.
5.
Plant Maintenance - Units 1 2 and
a
~
During the inspection period, the inspector observed and re-viewed documentation associated with maintenance and problem investigation activities to verify compliance with regulatory requirements, compliance 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 inspector verified reportabi lity for these activities was correc b.
The inspector witnessed portions of the following maintenance activities:
Unit 1 Descri tion Dates Performed o
Replacing a Cable Connector on The "D" Channel Supplemental Protection Amplifier.
12-20-87 o
Troubleshooting of Spurious Trip on RU-37.
12-22-87 o
Connector Reterminations on Valve SG-UV-172 Circuit Relay.
01-04-88 Unit 2 Descri tion o
Removing Steam Generator Level Channel
"C" Circuit Card From Cabinet Due To Problems With Setpoint Drift.
Dates Performed 12-21-87 Unit 3 Descri tion Dates Performed o
Charging Pump "A" Gear Box Replacement 12-15-87 o
ESFAS Actuation Relay Replacement 12-30-87 No violations of NRC requirements or deviations were identified.
6.
Verification of Containment Inte rit Unit 1 Prior to entry into Mode 4 on January 8, 1987, the inspector verified that the licensee had established containment integrity as required by Technical Specifications.
The inspector:
o Verified the operability of the containment spray system, o
Verified that all mechanical barriers and isolation valves associated with twelve containment penetrations were in their proper position, o
Witnessed the satisfactory completion of Procedure 73ST-9CL03,
"Airlock Local Leak Rate Test".
No violations of NRC requirements or deviations were identifie.
Containment Local Leak Rate Testin LLRT The inspector reviewed the licensee's program for the conduct of LLRTs.
The inspector reviewed procedure 73ST-9CL01,
"Containment Leakage Type B and C Testing",
and interviewed the test engineer responsible for containment leakage testing.
The inspector also examined the licensee's tracking system for LLRTs for all containment pressure boundaries and containment isolation valves, to ensure that LLRTs have been conducted at the required frequencies.
Finally, the inspector reviewed a sample of work orders for work performed on containment isolation valves to ensure that LLRTs were conducted where required.
No violations of NRC requirements or deviations were identified.
8.
Maintenance Pro ram Im lementation The inspector examined the implementation of the licensee maintenance program.
The inspector chose a random sample of maintenance work orders and verified the following characteristics:
o Vendor technical manuals were controlled and kept up-to-date.
o The instructions were adequate for the work involved.
o Administrative approvals were obtained.
o Functional testing was completed as necessary.
o PATE used was identified and in calibration.
o Parts and materials used were identified.
Other characteristics of the work orders verified by the inspector include:
o Procedures used conformed to the licensee's administrative requirements.
o Post-maintenance testing was appropriate.
o guality Control hold points were identified.
o The activity was described in sufficient details o
Hazards such as radioactivity were considered.
o Provisions were included for cleanliness and housekeeping.
Other attributes and characteristics were verified by the inspector, as applicable.
No violations of NRC requirements or deviations were identifie Desi n Chan es and Tem orar Modifications The inspector reviewed the licensee's design change program to ensure compliance with the minimum requirements.
A sample of individual Design Change Packages (DCPs)
was selected.
The inspector verified, as applicable, that the DCPs were reviewed and approved per the Technical Specifications and established guality Assurance controls.
The inspector ensured that tests were conducted to verify the acceptability of installed design changes.
Also verified were procedure and as-built drawing revisions to reflect the implementation of the design change.
Finally, the inspector verified that a mechanism existed to revise training programs to reflect the existence of a particular design change.
In addition, a review was conducted of the licensee's program for temporary modifications.
The inspector reviewed procedure 73AC-9ZZ05, "Temporary Modification Control", and verified the following items:
o Review and approval was in accordance with the Technical Specifications.
o Controls required the use of work orders for installation.
o A formal record was maintained of the status of temporary modifications.
o Independent verification was utilized both for installation and removal.
o Controls required functional testing.
o Periodic reviews were conducted of active temporary modifications to ensure that they were still needed.
No violations of NRC requirements or deviations were identified.
Licensed 0 erator Trainin The inspector reviewed the licensee's program for training and qualification of licensed operators.
The inspector interviewed training supervisors, reviewed training records for a sample of licensed operators, and attended a training lecture.
Also, procedure 82TR-9ZZ08, "Requalification Procedure for Licensed Operator Retaining" which describes the licensee's requalification training program was reviewed.
The inspector noted that the licensee's training program has been INPO accredited.
Training records for a sample of licensed operators were reviewed to verify the presence of certain records required to be retained by 10 CFR 55, Appendix A.
No deficiencies were noted, however, a problem was noted by the inspector with one licensed individual successfully completing the required requalification trainin The licensee's requalification program is divided into 16 separate courses taken over a two-year period (8 per year).
The Unit 3 Operations Manager has received an incomplete on 2 of the last 8 courses and received an oral upgrade in another course that was failed.
Further, this individual failed the yearly requalification exam.
ANSI 3. 1-1978, which the licensee has committed to, requires the Operations Manager to hold an SRO license.
This is even more important in Unit 3, since the new Plant Manager has little or no formal licensed operator training.
Licensee representatives stated that they were aware of the problem and were taking steps to correct it.
No violations of NRC requirements or deviations were identified.
11.
Followu Licensee Event Re ort LER
- Units 1 2 and
The following LERs associated with operating events were reviewed by the inspector.
Based on the information provided in the report it was concluded that reporting requirements had been met, root causes had been identified, and corrective actions were appropriate.
The below listed LERs are considered closed.
Unit 2 LER NUMBER DESCRIPTION 87-18-LO Spurious CREFAS.
Unit 3 LER NUMBER DESCRIPTION 87-01-00 87-02-00 Spurious CREFAS Spurious CREFAS No violations of NRC requirements or deviations were identified.
12.
Review of Periodic and S ecial Re orts - Units 1 2 and
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 information required to be reported by NRC requirements; test results and/or supporting information were consistent with design predictions and performance specifications; and the validity of the reported information.
Mithin this scope, the following reports were reviewed by the inspecto Unit 1 o
Monthly Operating Report for November and December, 1987.
Unit 2 o
Monthly Operating Report for November and December, 1987.
Unit 3 o
Monthly Operating Report for November and December, 1987.
No violations of NRC requirements or deviations were identified.
The inspector met with licensee management representatives period-ically during the inspection and held an exit on January 21, 1988.
During the exit meeting, the inspector discussed recent operating experiences involving personnel error emphasizing the need for greater attention to detail and management attention.