IR 05000255/1981005
| ML18046A667 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/15/1981 |
| From: | Boyd D, James Heller, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18046A666 | List: |
| References | |
| 50-255-81-05, 50-255-81-5, NUDOCS 8105220415 | |
| Download: ML18046A667 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/81-05 Docket No. 50-255 License No. DPR-20 Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Palisades Nuclear Generating Plant Inspection At:
Covert, MI Inspection Conducted:
March 1-20 and 22-31, 1981
~d Inspector~ B. ~;.)'
r J. K. Heller
~-
Approved By:
D. C. Boyd, Chief Reactor Projects Section lA Inspection Summary 4-/5-81 4-15-BJ 4-/5-8/
Inspection during March 1-20 and 22-31, 1981 (Report No. 50-255/81-05)
Areas Inspected:
Augmented resident inspection program activities including operations; surveillance; maintenance; reportable events; IE Bulletins and followup on previously identified item The inspection involved a total of 206 inspector-hours onsite by two NRC inspectors including 88 inspector-hours onsite during off-shift Results:
No items of noncompliance were identified in the areas inspected.
B 10.52201.//5
- DETAILS Persons Contacted
- kR. W. Montross, _General Manager
- J. S. Rang, Operations/Maintenance Superintendent
- H. J. Palmer, Technical Superintendent
- G. H. R. Petitjean, Technical Engineer B. L. Schaner, Operations Supervisor G. W. Ford, Senior Engineer (STA)
D. L. Morse, Assistant Mechanical Maintenance Supervisor D. W. Langschwager, Shift Supervisor A. F. Brookhouse, Shift Supervisor S. Ghidotti, Shift Supervisor A. S. Kanicki, Shift Supervisor D. W. Kaupa, Shift Supervisor E. I. Thompson, Shift Supervisor E. Polk, Assistant Mechanical Maintenance Supervisor W. E. Adams, Senior Engineer (STA)
- M. H. Okley, Quality Assurance Analysis
- S. Frost, Licensing Engineer (Jackson, MI Home Office)
- Denotes those present at Management Intervie Numerous other members of the plant Operations/Maintenance, Technical, and Chemistry/Health Physics staff were also contacted briefl.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of March 198 The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected component Tours of auxiliary and turbine buildings were conducted to observe plant equipment con-ditions, including potential fire hazards, fire extinguisher verified operable and in place, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspector by observation and direct inter-view verified that the physical security plan was being implemented in accordance with the station security pla A tour of the security fence was conducte The inspector observed plant housekeeping/cleanliness conditions and verified implementation of radiation protection control During the month of March 1981, the inspector walked down the accessible portions of the Component Cooling Water system to verify operabilit The in-spector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
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- These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and administrative procedure The plant operated at essentially full power throughout the month of March 1981, under the provisions of an NRC Immediate Action Letter (IAL) dated January 9, 1981, which was replaced by an NRC Confirmatory Order dated March 10, 198 Adherence to the IAL and Confirmatory Order was verified on a routine basi Provisions to delete items in the order were discussed with plant management during the monthly exit intervie A conference call between NRC Region III, Consumers Power Company and the NRC office of Nuclear React~f ~lgulation was held on March 27, 1981 to discuss inoperable snubbers.-
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The plant agreed (NRR concurred)
to immediately implement the requirements of Combustion Engineering Standard Technical Specification 3/4.7.9 dated October 17, 198 Consumers Power Company will submit a formal change to the Palisades Technical Specification at a later dat No items of noncompliance or deviations were identifie.
Monthly Maintenance Observation 1/
~/
Station maintenance activities of safety related systems and components listed below were reviewed to ascertain that they were conducted in ac-cordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specification MO 81-CIS-001 Repair of personnel airlock outer door handwheel MO 81-EPS-014 Monthly preventive maintenance on emergency diesel generator M0-81-CCS-005 Hot alignment of component cooling water pump P-52C MO 81-CVC-017 Repair of boric acid pump recirculation valve CV-2136 MO 51-ESS-003 Repair of safety injection accumulator pressure control valve CV-3038 MO 81-ESS-028 Repair and recalibration of safety injection accumulator level transmitter LT-0372 MO 81-ESS-032 Calibration of safety injection accumulator pressure indicator/alarm PIA-0371 IE Inspection Report No. 50-255/80-1 IE Inspection Report No. 50-255/80-24.
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The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certi-fied; radiological controls were implemented; and, fire prevention controls were implemente The inspector noted for MO 81-EPS-014 that signoffs provided on the controlling forms to indicate shift supervisor notification/author-ization were not complete This activity consists basically of an inspection of the emergency diesel and does not render any components inoperable or otherwise change the condition of component The plant Administrative Procedures clearly require involvement of the shift supervisor when installed plant equipment is to be made inoperable or its condition is otherwise altered by or for maintenance, but are less clear concerning activities of the type discussed her Some clari-fication in this area is deemed necessary, particularly since the NRC Order of March 10, 1981 (issued after MO 81-EPS-014 was completed)
addresses shift supervisor notification for testing activities, some of which also do not alter or render the subject components inoperabl This matter will be reviewed further during a future inspectio Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment main-tenance which may affect system performanc The following maintenance activities were observed: Changeout of overspeed trip switch on EDG 1-1 Calibration of instrumentation associated with EDG 1-2 Changeout of I-to-I package for subcooled margin monitor Following completion of maintenance on the above systems, the inspector verified that these systems had been returned to service properl No items of noncompliance or deviations were identifie.
Monthly Surveillance Observation The inspector observed Technical Specifications required surveillance testing on the systems/components identified below and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified
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during the testing were properly reviewed and resolved by appropriate management personne The inspector witnessed portions of the following test activities:
M0-7A Emergency Diesels M0-7C M0-8 M0-16 M0-11 M0-21 M0-22 Q0-5 Fire Pumps P-9A, P-9B and P-41 Primary and Secondary Computers PDIL Check and Control Rod Out of Sequence Alarm Inservice Test Procedure-Service Water Pumps Safeguards Boron Samples Inservice Pump Test-Concentrated Boric Acid Inservice Test Procedure: High Pressure Safety Injection Pumps Valve Test Procedure (includes Containment Isolation Valves)
Completed data for several tests performed in February 1981 were review-e Minor deficiencies in the form of incomplete signoffs (missing dates)
were noted in monthly Technical Specification Surveillance Tests M0-7B,
"Fire Pumps P-9A, P-9B, and P-41" and MC 11, "Safeguards Boron Sample."
Additionally, the inspector questioned the need to attach a calibration sheet of FI-0404A to monthly Technical Specification Surveillance Test M0-19, "Inservice Test of Containment Spray Pumps."
These items were discussed with licensee personnel at the monthly exit intervie No items of noncompliance or deviations were identifie.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to de-termine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Speci-fication (Closed) LER 80-34 and LER 80-39 "Inadequate Surveillance Proce-dure."
Licensee review of Q08, "ESS Check Valve Operability Test" and Q0-05, "Valve Test Procedure (includes Containment Isolation Valves)" determined that these procedures required manipulation of valves that would make a train of engineering safeguards equipment (ESF) inoperable or could damage ESF pumps if a safety injection signal (SIS) occurred coincident with valve testin Q0-8 required closing and reopening of the Safety Injection Refueling Water (SIRW)
tank outlet valves when determining the operability of the contain-ment sump outlet check valve Manipulation of these valves at hot
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- shutdown, as allowed by Q0-08, would disable a train of safeguards equipmen Q0-05 required stroking of the SIRW tank minimum flow recirculation valve Stroking of these valves coincident with an SIS could result in damage to ESF pump Q0-08 and Q0-05 have been revised to delete manipulation of the valve The valves have been added to Q0-02 "Recirculation Actuation System and Containment Sump check valves" which requires, as a prerequisite, the plant to be in cold or refueling shutdow (Closed) LER 80-41 "Diesel Generator/Charging Pump Inoperable."
With charging pump P-55C (associated with emergency diesel 1-1) inoperable, shift supervisor permitted emergency diesel 1-2 to be removed from service to perform the second cylinder leak tes (Closed) LER 80-042 "Steam Generator (S/G) Primary to Secondary Differential Pressure Limit Exceeded."
During plant cooldown the S/G differential pressure limit of Technical Specification 3.1. was exceeded for approximately 85 minute The operator performing the cooldown did not observe the out of specification conditio Upon discovery, Primary Coolant System pressure was reduced to return differential pressure limit to within limit Secondary water analysis and stress calculations were performed to assure that S/G tube integrity was maintaine Shift personnel involved were counseled and/or disciplinary action was take.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation in the bulletin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written respons (Closed) IE Bulletin 79-10, "Requalification Training Program Statistics." The licensee's letter dated May 23, 1979 provides the statistical data requested in the Bulletin, in the format as provided for by the Bulletin attachmen The requalification training program is routinely subject to NRC inspectio (Closed) IE Bulletin 79-21, "Temperature Effects on Level Measure-ments."
The licensee's letter dated September 18, 1979 addresses the Bulletin item The licensee did not propose setpoint changes (providing justification) but procedure revisions and attendent operator training have been accomplishe Subsequent to this re-sponse to this Bulletin, the licensee developed a design for automatic auxiliary feedwater initiation which will utilize the
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steam generator level instrumentatio Consideration of the implications of this Bulletin for that system function will be a part of the system modification revie (Closed) IE Bulletin 80-15, "Possible Loss of Emergency Notifica-tion System (ENS) With Loss of Offsite Power."
The licensee letter of September 4, 1980 addresses this Bulletin, clarifying the ENS power source and proposing an alternative test schedul Procedures for notification to NRC if the ENS system is determined inoperable have been prepare (Open) IE Bulletin 80-10, "Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment."
The licensee's letters of May 8, 23 and August 1, 1980 address potential clean and contaminated system interfaces; associated radioactivity monitoring, and mag-nitude of potential release The release path from the only system which has become cross-contaminated (plant heating boilers)
is a controlled and monitored pat Analysis indicates even failures or tank ruptures would not lead to the exceeding of 40 CFR 190 or 10 CFR 50, Appendix As part of his response, the licensee commited in his letter dated July 8, 1980, to expansion of sampling and analysis programs to include additional systems of the type addressed in the Bulleti Implementation dates were provide This commitment was implemented incompletely in that as of April 1, 1981, weekly sampling and analysis of the service air system (due date October,1 1980) were not being performe A special check of selected system components for contamination had been performed, the results showing no cross-contamination problem Supplementation of a routine sampling program was discussed with the responsible department head, who agreed to implement this ite This will be examined in a future inspectio No items of noncompliance or deviations were identifie.
Followup on Previously Identified Items Noncompliance items, IE Inspection Report No.. 50-255/80-21 (Closed) Item 1: Welding on the T-25B fuel oil day tank with no firewatch present at the scen (CLosed) Item 2: Removal from service of emergency diesel generator 1-2 when charging pump P-55C (associated with the other diesel generator) was inoperabl (See Paragraph 5, LER 80-041). (Closed) Item 3: During plant cooldown, the steam generator tube differential pressure was exceeded for approximately 85 minute (See Paragraph 5, LER 80-042)
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The licensee's actions as stated for the above in his letter dated December 16, 1980 were verified and considered appropriat Addi-tionally, for Item 1, the resident inspector has observed that the requirement for use of a firewatch is being complied with and that a firewatch, on February 25, 1981, took immediate action to extin-guish a small fire in the auxiliary buildin.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) throughout the month and at the conclusion of the inspection and summarized the scope and findings of the inspection activitie