IR 05000397/1985024
| ML17278A370 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/12/1985 |
| From: | Johnson P, Toth A, Waite R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17278A369 | List: |
| References | |
| 50-397-85-24, NUDOCS 8508290440 | |
| Download: ML17278A370 (18) | |
Text
U.S.
NUCLEAR REGULATORY COHMISSION
REGION V
Report No:
Docket No:
50-397/85-24 50-397 Facility Name:,,
Licensee:
Washington Public Power Supply System P. 0. Box 968 Richland, Wa.
99352 Washington',Nuclear Project No.'
(WNP-2)
Inspection at:
WNP-'2 Site near Richland,,
Inspection Conducted:
,
July 3 - August, 2, 1985 Inspectors:
Approved by:
WQ A. D. Toth,,Senior esident Inspector PQ I,
R.
S. Waite, Resident spector P.
H. Johnson, Chief Reactor Projects Section
(, IZ(bS Date Signed 5 iz85 Date Signed S(~ 85 Date Signed Summary:
Ins ection on Jul 3 - Au ust
1985 (50-397/85-24)
Areas Ins ected:
Routine, unannounced inspection by the resident inspectors of control room operations, engineered safety feature (ESP) status, surveillance program, maintenance program, licensee event reports, special inspection topics, and licensee action on previous inspection findings.
This inspection involved 184 inspection-hours on si.te by two resident inspectors, including 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> during backshift work activities.
During this inspection, inspection procedures 30703, 71707, 71710, 61726, 40700, 90712, 37700, 92700, 92701, 92702 and 93702 were covered.
Results:
No violations or deviations were identified.
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DETAILS Persons Contacted
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Powers, Plant Manager Corcoran, Operations Manager Beardsley, Assistant Operations Manager Landon, Maintenance Manager Graybeal, Health Physics and Chemistry Manager Feldman, Plant equality Assurance Manager Powell, Licensing Manager Muesterfeld, Reactor Engineering Supervisor
-"Personnel in attendance at exit meeting.
The inspectors also interviewed various control room operators, shift supervisors and shift managers, engineering, quality assurance, and management personnel relative to activities in progress and records.
2.
General i
The Senior Resident Inspector and/or the Resident Inspector were on site July 3-5, 8-12, 21-26, 28-31 and August 1-2,1985.
Pl Several regional office inspectors visited the site this month for inspection activities.
These activities were documented in other inspection reports.
These included:
A Reactor Projects Section Chief, (P. Johnson)
was on-site July 9-12.
A regional reactor inspector (P. squalls)
was on-site July 29 - August 2.
A regional reactor inspector (B. Albert) was onsite July 24-26.
An NRC investigator (O. Shackleton)
was onsite July 25-26.
3.
Plant Status The plant operated at reduced power most of July, at less than 50/ power using two recirculation system pumps at 15 Hz operation, and later at up to 72/ power using one pump at 60 Hz operation.
This was due to excessive vibration reappearing in the reactor recirculation system pumps after the maintenance outage which replaced the bearing to correct vibration observed in April. Also, a bearing failure at the beginning of the month made one feedwater pump inoperable for the July period.
4.
0 erations Verifications The resident inspectors reviewed the control room operator and shift manager log books on a daily basis for this report period.
Reviews were also made of the Jumper/Lifted Lead Iog and Nonconformance Report Log to verify that there were no conflicts with Technical Specifications and
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that the licensee was actively pursuing corrections to conditions listed in either log.
Events involving unusual conditions of equipment were discussed with the control room personnel available at the time of the review and evaluated for potential safety significance.
The licensee's adherence to Limiting Conditions for Operation (LCO's), particularly those dealing with ESF and ESF electrical alignment, were observed.
The inspectors routinely took note of activated annunciators on the control panels and ascertained that the control room licensed personnel on duty at the time were familiar with the reason for each annunciator and its significance.
The inspectors observed access control, control room manning, operability of nuclear instruments, and availability of on site and offsite electrical power.
The inspectors also made regular tours of accessible areas of the facility to assess equipment conditions, radiological controls, security, safety and adherence to regulatory requirements.
a.
Equipment Clearance Tags -
The inspectors examined the logs of outstanding clearance tags and noted that few of these involved
'safety related equipment at the current time.
The licensee operations and quality assurance organization has been monitoring this log and has taken steps to zeduce the number of outstanding tags, especially those which date back to 1982 and 1983. Additional actions are in progress and will be considered during routine inspection activities.
b.
Fire Protection Tours - The inspectors accompanied and interviewed equipment operators who were performing plant fire watch tours, especially of impaired fire barriers.
The operators in some cases were not familiar with exactly where the impaired barrier was located, but were accomplishing the intent of the tour via general observation of the wall, ceilings and floors of the area in which the barrier was designated on the check sheet.
The licensee management agreed to improve the attention to detail in this area.
No violations or deviations were identified.
5.
Surveillance Pro ram Im lementation The inspectors ascertained that surveillance of safety-related systems or components was being conducted in accordance with license requirements.
This period the inspectors observed several surveillance activities in-progress and noted the shift manager's log of such surveillances.
The inspector witnessed the performance of procedure 7.4.6.5.3.2, Standby Gas Treatment (SGT) Flow Test.
For this test, the technicians appeared willing to continue with the test, although the flow measurement probes could not be located into the precise chamber holes designated on the procedure.
The technicians did not complete the procedure and later consulted with the system engineer, which resulted in modification to the procedure.
The inspector discussed this matter with the plant manager with repect to the desirability of plant staff not proceding with a procedure if it becomes clear that the procedure and hardware do not coincide.
This is an additional element of the procedure accuracy matter defined as open item 84-22-0 l i
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No violations or deviations were identified.
6.
Licensee Action on 10 CFR 50.55(e)
and
CFR 21 Deficienc Re orts Various construction deficiency reports were issued by the licensee during the construction phase of the project.
Those reports of conditions and corrective actions taken or planned were reviewed by NRC regional staff at the time of submission.
Fulfillment of reporting requirements, report completeness, corrective actions, generic aspects of the items, and ne'ed for onsite followup were evaluated.
Many of these reports were further examined during followup inspections of records and hardware at the site.
In some cases NRC in'spection staff deferred the closeout of NRC followup actions.
These reports have been re-examined and assessed to identify need for additional NRC followup inspection.
The results of the review'are as follows:
a.
Item 79-09-A Licensee Re ort Number 44 - Pum Room Floodin Due To Fuel Pool Boil-off This item was first reported in 1979. It has been addressed in subsequent interim and final reports through 1982. It was discussed in NRC inspection report 82-17, which noted a planned amendment to the FSAR to clarify piping ASME Code classifications and system modifications.
The NRC Safety Evaluation Report of March 1982 recognized the revised design of the fuel pool cooling system, and commitment for completion of the modifications prior to first refueling.
The current Amendment 30 to the FSAR (June 1983)
includes figure 9.1-4, which clarifies code classifications of piping.
The inspector observed that fuel pool modifications were in progress through 1985.
This matter is closed.
b.
Item 82-12-,B Iicensee Re ort Number 218 - Valve not owered from class 1E ower su l main steam isolation valve leaka e collection
~ss tern This item was first reported November 1982 during the construction reverification program.
In NRC inspection report 83-24 the inspector questioned the implications of this matter with respect to other plant systems.
Subsequently the preoperational and power ascension testing programs were conducted, providing additional confidence that the the safety systems could function upon loss of normal power sources.
Another Licensee Report (Number 291, item 83-ll-C below)
was reported as a result of such test preparation activities. This matter is closed.
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Item 83-01-F Licensee Re ort Number 229 - Missin Pi e Han ers This item was first reported January 1983. It has been addressed in a subsequent final report May 1983 and NRC inspection report 83-24.
The resident inspector had interviewed personnel regarding the use of the Hanger Checklist shortly after this event.
The more general plant wide aspects of this pipe support discrepancies were identified during subsequent NRC construction assessment team
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inspections and associated corrective actions were taken and found acceptable by NRC.
This matter is closed.
Item 83-10-C Licensee Re ort Number 290 - Diesel Generator Exciter Control Cabinet Overheatin This item was first reported September 1983 during preoperational, testing.
Corrective actions were described in the report as including'odification of the cabinets to increase cooling.
During the exit meeting, the licensee committed to assure that seismic qualification of the equipment cabinets had been considered during generation of the design change package.
This matter is closed based upon in-office review of the event report, and with exception of the one item identified at the exit meeting.
Item 83-11-B Licensee Re ort Number 296 - HFA Rela s
Centur Series 151A9F I,pose Internal Assembl Screws This item was first reported November 1983 during WNP-2 preoperational testing, and has 'been addressed by the licensee, in addition to other HFA relay issues identified by INPO, NRC and vendor information correspondence.
The licensee advised the vendor (GE) on November 16, 1983 that this matter may involve 10 CFR 21.
To date, the MPPSS files show that neither a
GE Service Information Letter nor Part 21 Report have been issued.
MNP-2 requirements were met via the
CFR 50.55e report.
This item is closed except for the open item identified at the exit meeting.
Item 83-11-C Iicensee Re ort Number 291 - Valves not owered from 1E ower source Containment Atmos heric Control S stem This item was first reported October 1983 during preoperational testing. It was similar to Item 82-12-B (above)
and demonstrated the preoperational testing engineer involvement and effectiveness in review of circuit details as part of preparing the testing and system lineup documents.
This item is closed.
Item 83-12-B, Licensee Re ort 295 - Standb as treatment s stem unit charcoal filter bed leaka e
f This item was first reported November 1983 during the preoperational testing program.
The resident inspector at that time witnessed the repairs o'f the filter frames to fill'aps through which charcoal grains were being lost.
This matter is closed.
Item 83-12-C I,icensee Re ort 299 Room Pressurization due to hi h ener line breaks This item was reported September 1983 during the construction completion program.
Related matters were described in the license event report LER-85-001.
This matter's closed based upon in-office review of the corrective actions described in the licensee report I J
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Item 83-12-D Iicensee Re ort 302 - Undervolta e rela roblem in hi h ressure core s ra s stem This item was reported November 1983 during preoperational testing.
At that time the inspe'ctors identified design changes in progress to resolve this item,",,and incorporation into preoperational tests.
The NSSS contractor was involved"to assess generic considerations.
This matter is closed.
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Item 83-12-E Licensee Re ort Number 306 - H dro en recombiner scrubber draina e
roblem This item was reported December 1983 during the preoperational testing program..This'atter is clos'ed based upon in-office review of the corrective actions'escribed
.in the licensee report.
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gp Item 83-12-F Licensee Re ort Number;307 - Tar et rock solenoid valve ad ustment h draulic"control lines of recirculation s stem flow control valves This item was reported De'cember 1983 during the preoperational testing program.
This matt'er is closed based upon in-office review of the corrective actions described in the licensee report.
f Item 83-12-G Licensee Re ort Number'03 - Incorrect installation of solenoid valve h draulic control lines of recirculation s stem flow control valves This item was reported December 1983 during the preoperational testing program.
The NRC resident inspector subsequently observed that repairs had been scheduled and completed to resolve this item.
This matter is closed.
No violations or deviations were identified.
7.
Licensee Actions On Previous NRC Ins ection Findin s The inspectors reviewed records, interviewed personnel, and inspected plant conditions relative to licensee actions on previously identified inspection findings:
a
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(Closed) Followu Item (85"19-01) - Diesel enerator load discre ancies a
eared in FSAR tables 8.3-1 throu h 8.3-3 The licensee electrical engineering, department reviewed the tables and identified needed clarifications, including addition of a Note to clarify that kilowatt values in some cases included consideration of auxiliary heaters and equipment efficiencies, in addition to motor horsepower values.
The corrections are being processed for the next amendment to the FSAR.
The draft amendment documents the engineering confirmation that the corrected generator loadings do not exceed the unit ratings of 4400 KM eac t i
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b.
(Closed) Followu Item (85-21-01) Omission of reactor buildin to wetwell vacuum relief rilles In response to comments by NRC technical reviewers, the licensee had initiated an FSAR change notice (SCN) to install these grilles.
During the period this SCN was being evaluated, Burns and Roe analysis confirmed that the screens were not required and NRC verbal concurrence was obtained.
In-process field direction to install the grilles was revised, apparently without knowledge that the revised FSAR issuance was already in-progress.
Therefore, the engineer referral to the FSAR showed no inconsistency and a need for further FSAR correction was not recognized.
The licensee has now initiated an SCN to delete the grilles, reflecting the original FSAR configuration.
Documentation of the NRC position was not locatable, therefore the licensee has now reaffirmed the understandings in writing to the NRC licensing organization.
This appeared to be a
unique error associated with returning the system configuration to that originally shown in the FSAR and associated time lapses for publication.
No deviations or violations,were identified.
8.
S ecial Ins ection To ics The inspectors emphasized review of licensee activities in the following areas this month:
a
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Activities of the Plant 0 erations Committee (POC)
The inspector commenced a general review of the activities of the POC this period, which included attendance at two meetings.
These POC meetings involved key "plant management, as described in the Technical Specifications, and involved a typical 4-hour duration and longer.
,The inspector also reviewed the governing procedure, which appeared to comply with the Technical Specification requirements.
The POC meetings included review and discussion of current plant status.
Additionally it was noted that the key managers who constitute the POC also convene each morning to review plant status, and in particular the shift manager log for the prior day and evening.
The daily meetings were routinely attended by a shift manager representative to provide additional details of the plant status.
The inspectors conclusions will be documented when the inspection activities have been completed.
No violations or deviations were identified at this time.
b.
Alle ation (RV-85-A-035) Containment Ventilation Balancin Characterization of Alle ation The alleger stated that personnel working for Able Balancing Company were performing work at MNP-2 for which they were not qualifie 'P W
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Specifically, they did not'elong to the union of heating and ventilation crafts.
Im lied Si nificance to Desi n-Construction-0 eration If unqualified personnel effected changes to the containment cooling system it is possible that such changes may be incorrect in such a
way that the system would fail unexpectedly in service under accident conditions, or would under normal conditions not be capable of maintaining containment atmosphere temperatures below values at which degradation of accident mitigating equipment would occur at accelerated rates.
For normal conditions, Technical Specifications establish limits on, and requirements to monitor such temperatures, such that cooling system performance inadequacies would be detected when the plant was placed into operation and actions taken to correct the situation.
However, such monitoring would not necessarily reveal construction defects which would materialize only under accident conditions.
In regard to membership in a labor union, there are no NRC requirements in general for such membership.
Assessment of Safet Si nificance The inspector reviewed the quality-related work being performed by Able Balance Company.
The company was a contractor employed on site during the maintenance outage to assist in the performance of containment ventilation balancing.
The company personnel solely performed measurements and acted as consultants, with the actual balancing being performed by WNP-2 maintenance personnel.
The company personnel were not involved in any construction work on the system, and thus were not susceptible to introduction of hardware defects.
The company personnel were involved in making measurements of air flows for evaluation and action by the WPPSS plant technical staff.
Any errors by the company staff would appear to be identifiable during the subsequent special and routine performance monitoring of containment temperature control. It is not likely that an unidentifiable defect could be introduced by actions of the company personnel.
However, the inspector examined the qualifications of those personnel employed by Able Balance on site.
The two lead personnel of the company team were found to have had experience in system balancing of 4 years and twenty three years.
Also, individual team members had schooling ranging from training at technical schools to an Associate of Science degree in Mechanical Engineering.
The other two personnel assigned to the site were paired with the lead individuals.
The personnel employed by Able Balance in a team capacity at. WNP-2 appeared to be qualified for performance of system'alancin I P
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Conclusion The allegation was not substantiated.
There was no evidence that safety related construction or operation was compromised nor that general or specific NRC requirements were violated.
c.
Plant Drawin U dates The inspector reviewed licensee procedures 1.4.1, "Plant Modifications" and 1.6.2, "Control of Drawings and Support Data".
'he inspector selected a representative sample of several design changes and verified that, all th'e related top tier drawings were red-lined or revised as required per these procedures.
The inspector also reviewed a'ite QA surveillance on this subject which identified no discrepancies.
No violations or deviations were identified.
9.
Mana ement Meetin The inspector met with the'project manager approximately weekly during this period, to discuss inspection finding status.
On August 2, the inspectors met with the Plant Manager and members of his staff to discuss the inspecton findings during this period.
At the management meeting, the inspector identified the following open items relating to 10 CFR 50.55e reports, and requested specific information as noted below:
a.
Licensee report No.
290 - The inspector requested data to verify that seismic qualification of deisel generator exciter cabinets had not been compromised by modifications for additional ventilation.
Open item (85-24-01).
b.
Licensee report No.
296 - The inspector requested data to demonstrate that future procurements of HFA Century Series relays will provide for verification that internal coil mounting screws are properly torqued before putting the relays into service.
Open item (85-24-02).
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