IR 05000255/1979009
| ML18043A982 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/27/1979 |
| From: | Boyd D, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18043A981 | List: |
| References | |
| 50-255-79-09, 50-255-79-9, NUDOCS 7908280233 | |
| Download: ML18043A982 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/79-09 Docket No. 50-255 Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Palisades Nuclear Generating Plant Inspection At:
Palisades Site, Covert, MI Inspection Conducted:
June 11-14 and 20-22, 1979
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Inspector:
B. L. Jor~:'{'rf~
- (}/!~"/cf Approved By
D. C. Boyd, Acting Chief Reactor Projects Section 3 Inspection Summary License No. DPR-20 Inspection on June 11-14 and 20-22, 1979 (Report No. 50-255/79-09)
Areas Inspected:
Routine, unannounced inspection of operations, fire protection, reportable events, and licensee action on previously iden-tified items and on IE Bulletin The inspection involved 47 inspector-hours onsite by one NRC inspecto Results:
No items of noncompliance or deviations were identified in any of the areas inspecte DETAILS Persons Contacted *H. Keiser, Operations and Maintenance Superintendent
- K. Berry, Technical Superintendent
- J. Liddell, Training Supervisor
- G. Gilbody, Quality Assurance Engineer
- G. Petitjean, Technical Engineer R. Vincent, Senior Engineer B. Harshe, Senior Engineer D. Kozin, Chemistry Supervisor R~ Mieras, Shift Supervisor A. Brookhouse, Shift Supervisor E. Thompson, Shift Supervisor
- Denotes those present at the exit interview on June 22, 197 The inspector also had discussions with several members of the plant operating staf Licensee Actions on Previous Inspection Findings (Closed) Noncompliance Item (50-255/79-04):
Failure to follow procedures for control of field changes made during maintenanc The inspector reviewed the licensee's actions as stated in his letter of March 30, 1979, including identification and evaluation of any other discrepancie Six such discrepancies were found, all of which occurred before the requirements of the cited procedures were in existenc Four of the items were determined to require corrective action, which has been complete A safety analysis established the acceptability of the remaining two item (Closed) Noncompliance Item (50-255/78-30):
Failure to complete required annual review of the training program for the plant main-tenance departmen The inspector reviewed licensee actions described in his letter dated February 15, 197 Program review was completed for 1979, as stated, by the training departmen This review covered training programs for all the plant department Functional supervisory evaluation then consisted of discussions between functional supervisors and the training department con-cerning review results, identified needs, and future functional training program plannin.
Reportable Events The inspector reviewed the licensee's actions on the following event reports to ascertain they were properly reviewed, evaluated and
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(_)
reported, corrective actions were taken as appropriate, and plant
. limits were not exceede Both records and personnel interviews were used in the revie LER 78-33:
Unplanned gaseous radwaste r~727se. Most aspects of this item were evaluated and reported- -
previousl This inspection included the determination that leaky gas decay tank had been repaired and successfully leak teste This item is close LER 78-40:
Unplanned gaseous radwaste releas Radiologica131 aspects of this event were previously evaluated and reported.-
This inspection verified operator re-instruction and malfunc-tioning drain trap repai Modification of the drain trap to improve reliability is being considere This item is close LER 79-01:
Inadequate RPS bypass key contro The event was reviewed with cognizant personnel and was added to and covered during conduct of the routine operations training curriculu This item is close LER 79-04:
Failure to meet minimum equipment operability requirements and to perform required redundant equipment operability demonstratio The event was reviewed with cognizant personnel and covered during routine operations trainin Shift logbook maintenance practices have been revised to require identification and logging of all out-of-service safety equipment at the beginning of each shif This item is close * LER 79-05:
Inoperable emergency diesel-generato The EDG was rendered inoperable by failure of a component (fuel oil filter drain tap) which had been recently installed without first completing required evaluation and approva Modification of the EDG in this unauthorized fashion result~J in noncompliance as identified during a previous inspection.-
Based on followup on the noncompliance item, described in Paragraph 2 above, this reportable event item is also close LER 79-08:
Safety Injection Tank pressure outside limits in excess of one hou A short across the fill valve and vent valve controls was discovered to result from metal filings 1/ IE Inspection Report No. 50-255/79-0 /
IE Inspection Report No. 50-255/79-0 / Ibi !I IE Inspection Report No. 50-255/79-0 *
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found in the common connector at the containment penetratio The filings were removed and the connector replaced and satis-factorily teste The filings are believed to have been present since original installatio Licensee personnel are unaware of any similar previous failure This item is close LER 79-09:
Containment purge supply and exhaust valves deter-mined incapable of operation to isolate against postulated accident pressure The valves have been demonstrated to meet isolation and leak-tightness requirements again~76
,ccident pressures when they are in the closed position.- -
The licensee has instituted'measures to assure these valves remain closed at all times the primary coolant system is above 210 degrees This item is close No items of noncompliance or deviations were identifie.
IE Bulletins 5/
°§_/
The inspector reviewed the licensee's actions concerning the following IE Bulletins. IEB 79-04:
Incorrect weights for swing check valves manu-factured by Velan Engineering Corporatio The licensee determined none of this manufacturer's swing check valves were installed in safety-related systems where diameter exceeds three inche IEB 79-07:
Seismic stress analysis of safety-related pipin None of the identified problematical analytical methods were used in seis_mic computer analyses for Palisades plant safety- _
related pipin Computer programs which were used had benchmark verifications performe IEB 79-09:
Failures of GE Type AK-2 circuit breakers in safety-related system The licensee determined circuit breakers of the identified type have not been installed in safety-related systems at Palisade For items a. through c. above, licensee evaluations and actions were deemed appropriat No further information is required concerning these items; they are considered close The inspector reviewed and discussed the status of licensee actions with respect to two additional IE Bulletin IE Inspection Report No. 50-255/78-0 IE Inspection Report No. 50-255/78-28.
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-- IEB 79-03:
Longitudinal weld defects in ASME SA-312 type 304 stainless steel pipe spools manufactured by Youngstown Welding and Engineering Compan The licensee had determined none of the identified material had been specified for use in safety-rela ted system A review to ascertain whether any field changes completed subsequently may have substituted the iden-tified material for that specified is underwa IEB 79-06B:
Review of operational errors and system misalign-ments identified during the Three Mile Island Inciden Reviews are complete, as are most procedural change Plant modifications have been identified and planned but delays in receipt of qualified safety-grade materials and components has delayed their completio A special committee formed to evaluate TMI implications for the design and operation of the Palisades Nuclear Generating Plant continues to be activ For items d. and e. further review is required at a future inspectio No items of noncompliance or deviations were identifie.
Facility Operations The inspector reviewed operations records and activities to verify compliance with license requirements, Plant Startups The inspector reviewed startup checksheets, logs, and I/M plots relating to several unit startups in April, May and June 197 The Shift Supervisor's Logbook noted problems with one startup channel in early April and, in fact, the plant was taken critical on April 8 and 26 and on May 1, 1979, with only one properly operating startup channe This is permitted by the Technical Specifications provided specified conditions relating to the shutdown neutron power levels and responses of the log range channels are me Licensee documentary evidence of adherence to these conditions was not clea Discussions with licensee personnel strongly indicate they were me Recognition of and documentation showing compliance with such special requirements was discussed with licensee personnel at the exit intervie Shift Supervisor's Logbook:
April and May, 1979 Control Room Logbook:
April and May, 1979 On April 4, 1979, the plant operated at full power while the steam-driven auxiliary feedwater pump and emergency diesel-generator 1-1 (which provides vital power for the motor-driven
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auxiliary feedwater pump) were concurrently out of service for about one hou Though this condition is not spoken to by the Technical Specifications it places the plant in a condition not considered in the accident analyse That is, a complete loss of offsite power (several of which have been experienced) would leave the plant with no means to remove decay heat until restor-ation of one of the inoperable component This would have to be accomplished within about 16 minutes to prevent the steam generators boiling dry and producing potentially severe temper-ature conditions in the primary syste Licensee personnel concurred with this evaluation and stated they had recognized the situation soon after it developed and returned the inoperable components to service as quickly as possibl The licensee has proposed certain Technical Specification additions relating to auxiliary feedwate This matter will be identified to the NRC Office of Nuclear Reactor Regulation with a request for the establishment of appropriate controls in the Technical Specif i-cation This matter was also discussed at the exit interview, and is considered an open ite Daily Orders Logbook:
April and May, 1979 Secondary Plant Chemistry Data relating to analyses and results for the secondary plant chemistry monitoring program were reviewed during this inspec-tion, and discussions were held with plant chemistry personne Due to condenser tube leakage which developed in late May, 1979, the new condensate demineralization system was placed in service from June 4-9, 197 This resulted in oscillations in steam-generator pH outside established limits on several relatively brief occasion The time limits provided by Technical Speci-fication action statements were not exceede The system failied to prevent sodium buildup as desired, and the licensee therefore is re-evaluating the system and the chemistry para-meters for the secondary side.,Little experience has been gained to date in system operation, which may have contributed to operational problems experienced during the June ru Radwaste Logbook (Primary-side auxiliary operator's log):
April and May, 1979 Caution Tag Log:
April and May, 1979 Control Room Operations Routine facility operations were observed in the. control room at various times during this inspectio The observations included a power escalation from about 50 percent to essentially
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. * * (~-) full powe Also noted were shift manning and turnover and operator awareness of system and component status.
No items of noncompliance or deviations were identifie Fire Protection This inspection included a tour of various plant locations (unaccom-panied by licensee representatives) to observe the condition of critical fire area The locations inspected included the control room, the cable spreading room, both vital 2400 v. bus rooms, both emergency diesel-generator rooms, the vital switchgear room, both station battery rooms, and selected engineered safeguards area No combustible materials were noted, nor was any work in progress involving open flame or other ignition source All fire doors were found close Fire extinguishers and hose stations appeared in good conditio Minor obstruction of one extinguisher and one hose reel were noted during an initial tour on June 14, 197 Before the completion of the inspection the inspector learned the licensee had performed his monthly surveillance of fire stations on June 17, 197 A second tour then established the obstructions had been cleared during this surveillance, without their having been identi'fied to licensee personnel by the inspecto No items of noncompliance or deviations were identifie Management Interview A management interview attended by licensee personnel noted in Paragraph 1 above, was conducted at the conclusion of the inspection on June 22, 197 The inspector described the scope and findings of the inspection as described in these Detail The following items were specifically discussed: Critical approaches with one startup channe (Paragraph 5) Operation with the steam-driven auxiliary feedwater pump and emergency diesel-generator 1-1 concurrently out of servic (Paragraph 5.c) Probl~ms with the condensate demineralization syste (Paragraph 5.e) Action status on reportable events (Paragraph 3) and IE Bulletins (Paragraph 4).
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