IR 05000255/1980003
| ML18044A871 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/20/1980 |
| From: | Boyd D, James Heller, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18044A870 | List: |
| References | |
| 50-255-80-03, 50-255-80-3, NUDOCS 8005140275 | |
| Download: ML18044A871 (5) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
8 0051409-7~
~eport No. 50-255/80-03 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:
Palisades Site, Covert, MI Inspection Conducted:
February 4-8,11,12,14,15,19-22 and 25-29, 1980 48~-(~
Inspectorsf"-B. ~K's; rJ. K.;~":(,,t_
Approved By: D. C'B~d~hief Reactor Projects, Inspection Summary 3-zo-80 3-20-80 Section 3-1 Inspection during February, 1980 (Report No. 50-255/80-03)
Areas Inspected:
Routine resident inspection program activities during February, 1980, including:
inspection during long-term shutdown; report-able occurrences; and actions on IE Bulletins and NUREG-0578 item The inspection involved 78 inspector-hours onsite by two NRC inspector No items of noncompliance or deviations were identified in the areas in-specte Results:
No items of noncompliance or deviations were identified in the areas inspected.
- DETAILS Persons-Contacted
- J. G. Lewis, General Manager, Palisades *H. J. Palmer, Technical Superintendent B. L. Schaner, Operations Supervisor B. L. Harshe, Senior Engineer R. A. Vincent, Senior Engineer R. L. Ritt, Senior Technical Analyst *G. H. R. Petitjean, Technical Engineer G. W. Ford, General Engineer C. E. Smith, Shift Supervisor A. S. Kanicki, Shift Supervisor R. Bennett, Plant Instructor Several other members of the plant operations and technical staffs were also briefly contacte *Denotes those present at management interview on February 29, 198.
Activities During Long Term Shutdown The inspectors reviewed selected licensee activities being carried out during the current shutdown condition to ascertain compliance to applicable requirement Control Room A number of visits to the control room verified adherence to limiting conditions for operation at cold shutdown, proper shift manning, adherence to selected procedures, and in-strument/recorder operatio Selected operations logs were reviewed to maintain current knowledge of plant and system statu Facility Tours Tours of selected accessible plant areas, including the containment building, were conducted to assess equipment and plant conditions, radiological controls, security, and general safet A few questions or minor problems were identified and discussed with licensee personnel, including:
storage of the thermal shield on pedestals near the reactor cavity; spark control from a welding operation on the "B" steam generator feedline; positive access controls for a potential entrance/exit of the radiation controlled area; and numerous apparently burned-out indicator lights on the C-33 (shutdown)
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pane Where appropriate, the licensee initiated corrective measures responsive to the indicated minor problem No items of noncompliance or deviations were identifie.
Reportable Events The inspectors reviewed the licensee's actions for the following event reports to verify proper review and evaluation, corrective action, and compliance with associated license requirement Re-cords and personnel interviews were used in the revie LER 79-38:
Service water pump P-7c discharge check valve failed to ope Disassembly and examination of the valve internals during the current outage revealed a generally de-teriorated condition, more significant than the expected hinge pin corrosio All three service water pump discharge check valves were ultimately removed in sequence, returned to the manufacturer for remanufacture/overhaul, reinstalled, and satisfactorily teste This item is close LER 79-41:
Safety analysis nonconservative in that exessive steam-generator feed by the condensate pumps, following a main steamline break without loss of offsite power, was not con-sidere A facility modification was performed to isolate the main feed flowpaths, including condensate, on low steam genera-tor pressur The inspectors discussed the modification with plant engineering staff, reviewed the facility change package, and witnessed successful pre-op testing of the modified syste This item is close An outstanding inspection item concef~ing the same subject, identified during a previous inspection -
is also considered closed based on the review discussed abov Note:
IE Bulletin 80-04 addresses similar concerns, but with a broader scop The licensee's actions on Bulletin 80-04 will be reviewed during a future inspectio LER 79-42:
Lift settings of two pressurizer code safety valves out of specification. All three safety valves were tested on steam during the current outage because the licensee received information that his standard test using cold nitrogen could be insufficiently accurat The valves were reset and retested within specification. Future testing will be done on stea The inspectors reviewed the test report and the documentation covering procurement of the testing service This item is close No items of noncompliance or deviations were identifie !/
IE Inspection Report No. 50-255/78-13
- 3 - IE Bulletins and NUREG 0578 This inspection included a review of licensee activities relating to requirements of IE Bulletin based on the accident at the Three Mile Island Nuclear Plant and of NUREG 0578 "TMI-2 Lessons Learned Taskforce Status Report and Short-term Recommendations."
P~oper completion of many of these items constitutes a prerequisite to plant startup following the current outag The items can be categorized as facility items (modifications to systems and components) and procedure item Procedure items will be reviewed in detail during a future special inspectio IE Bulletin 79-06B:
Many of the specific requirements of this Bulletin w27e reviewed and reported on during a previous in-spection. -
One facility item, relating to containment auto-matic isolation in NUREG 057 This inspection included dis-cussion with the project engineer concerning possible modi-fication Final review of facility items relating to auto-matic containment isolation will be completed during a future inspectio The several remaining procedure items will also be reviewed during a future inspectio One item, however, relating to notification of the NRC within one hour of uncontrolled/un-expected plant conditions, has been superseded by a Commission rulemaking noticed in the Federal Register (February 29, 1980)
which specifies for all power reactor licensees new one-hour notification requirements, including uncontrolled/unexpected plant condition For the purpose of IE Bulletin 79-06B, this item is close NUREG 0578:
The following facility items were discussed with the assigned project engineer(s) and an initial review of the modification packages was performed during this inspection:
(1)
Provision of emergency power to pressurizer heater (2)
Provision of direct pressurizer relief and safety valve position indication (3)
Provision of instrumentation for identifying inadequate core cooling (4)
Leak testing of systems which could contain highly con-taminated fluids (5)
Provision of auto-start system for auxiliary feedwater
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IE Inspection Report No. 50-255/79-07
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(6)
Provision of safety-grade auxiliary feedwater flow in-strumentation (7)
Provision of qualified power supply for pressurizer relief valves and the associated block valves Concerning item (5) above, the modification has been designed and is being installed with the exception of final connections, pending further safety review Concerning item (7), the subject valves, except PORV 1043B, have always been on vital powe The modification to supply 1043B, have always been on vital powe The modification to supply 1043B on vital power is complete and was reviewed by the inspector, including satis-factory pre-operational testin Item (7) above is considered close No item of noncompliance or deviations were identifie.
Management Interview A management interview, attended as noted in Paragraph 1 above, was conducted following the conclusion of the inspection on February 29, 198 The inspectors discussed the scope and findings of the in-spection as described in these Detail