IR 05000255/1979013
| ML18043B115 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/17/1979 |
| From: | Boyd D, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18043B114 | List: |
| References | |
| 50-255-79-13, NUDOCS 7910250044 | |
| Download: ML18043B115 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/79-13 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:
July 30-31, August 1-3, 6-10, 13-17, 20-24, 27-28 and 30-31, 197 /'
Inspector:
B. ~~
9-/7-79
~C7'_,~L c;-/7-7° Approved By:
D. C. Boyd~i~f
Reactor Projects Section 3 Inspection Summary Resident Inspection for August, 1979 (Report No. 50-255/79-13)
Areas Inspected:
Routine resident inspection for August, 1979, covering plant operations; safety limits, limiting safety-system settings and limiting conditions for operation; procedures; maintenance; and new fuel receipt The inspection entailed 133 onsite direct inspection hours by the NRC Resident Inspecto Results:
No items of noncompliance or deviation~ were identified in any of the inspected area I
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DETAILS Persons Contacted *J. G. Lewis, General Manager-Palisades H. W. Keiser, Plant Superintendent
- C. H. Gilmor, Maintenance Superintendent C. Thomas, Mechanical Maintenance Supervisor R. D. Story, Assistant Mechanical Maintenance Supervisor J. A. Meineke, Reactor Engineer
- B. L. Schaner, Operations Supervisor R. E. Mieras, Plant Shift Supervisor A. F. Brookhouse, Plant Shift Supervisor E. I. Thompson, Plant Shift Supervisor D. W. Kanpa, Plant Shift Supervisor A. S. Kanicki, Plant Shift Supervisor
- G. H. R. Petitjean, Technical Engineer J. S. Everett, Quality Control Inspector W. A. Binnington, Quality Control Inspector R. F. Bales, Quality Control Inspector P. E. Cherry, Senior Instrument and Control Technician
- Denotes those present at the management interview on August 31, 197 The inspector also had discussions with several other individuals from the operations and maintenance staffs.
Facility Operations Control Room Activities This inspection included a review of control room activities on most inspection days. Plant and equipment status, tagging, alarms or off-normal conditions, and facility manipulations were reviewed and discussed with operating staff personne Control room manning was specifically checked on numerous occasion Pursuant to I.E. Bulletin 79-06C, the licensee is continuously providing two licensed operators in the control room at all times, during power operation This activity commenced July 30, 197 On several occasions, direct observations were made of process instrumentation, control consoles, panels and annunciator boards to verify licensee operations in compliance with safety limits, limiting safety-system settings, and limiting conditions for operatio One or more technical specification requirements were checked for each of the following:
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(1) Reactor Coolant System (2) Reactivity and Power Control (a) Reactor Control System (b)
Chemical and Volume Control System (3)
Power Conversion Systems (4)
Containment Systems (5) Electrical Systems (6)
Engineered Safety Features (a)
Component Cooling,
(b)
Service Water (c) Auxiliary Feedwater (d)
Safety Injection Tanks Emergency diesel-generator 1-1 was out of service for maintenance on two occasions and once failed to start during testing, which necessitated additional maintenanc Also, two different thermal margin/low pressure reactor trip channels required maintenance, as did one of the charging pump For these items, the inspector verified adherence to tagging and minimum equipment operability requirement This required an interpre-tation from NRC's Office of Nuclear Reactor Regulation when EDG 1-1 and one of two charging pumps associated with EDG 1-2 were out of service concurrently. It was determined, since only one charging pump is capable of operation off emergency power whenever EDG 1-2 is inoperable, that only one of the two charging pumps on EDG 1-2 need be operable when EDG 1-1 is inoperable.
The licensee has developed a smaller caution tag for identifying off-normal conditions, with the choice of which type tag t~
use being at the operator's discretio A previous inspection-identified a few indications, none in safety-related systems, were obscured or partially obscured by caution tag During this inspection period no obscured or partially obscured indicator lights were note Unit trips from significant power levels occurred on August 10, 1979, and on August 24, 197 In each case, a control operator manually tripped the unit following loss of main feedwate The inspector reviewed selected records, charts and process computer information for the trip of August 1 For the trip of August 24, the inspector was present and directly observed control room operations from a few seconds after the tri Both events were accomodated without incident; systems and components all functioned as designed; and control room activities on August 24 appeared orderly and well-coordinate !/
IE Inspection Report No. 50-255/79-0 ~ Operations Logs The inspector maintained a current review status for the following logs:
(1) Daily Orders Logbook (2) Shift Supervisor's Logbook (3)
Control Room Logbook (4)
Reactor Logbook (5)
Caution Tag Record and Jumper/Bypass Log Log entries were considered appropriat Sufficient detail is provided to discern equipment off-normal condition Licensee supervisory review and an independent review for possible reportable items are both provided fo The inspector noted one of two Secondary Position Indication (SPI) reed-stack "jumpers" was recorded in the Jumper/Bypass Log while the other was documented in the Caution Tag Recor Both were tagged as require The inspector also noted several jumpers/bypass (most not in safety-related systems) which have been in place a considerable tim The licensee reviews and updates tags in safety-related systems as needed for tag legibility. Discussions were held with licensee personnel concerning whether long-term installations should be considered "permanent", and processed as facility modifications so the number of log entries and tags can be reduce Checksheets The inspector reviewed selected hourly, shiftwise and daily checksheets to verify proper completion and to determine compliance to selected limiting conditions for operation and to plant safety limit Facility Tours Various plant areas were toured during this inspection period for determination whether abnormal or unsafe conditions existe Particular attention was given to system/component operability requirements stipulated by technical specification limiting conditions for operatio No items of noncompliance or deviations were identifie.
Procedures Several licensee procedures were examined during this inspection to determine technical adequacy; consistency to license requirements;
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and proper development, review, approval, and revisio The inspector routinely receives and reviews changes to plant Administrative Procedures and Operating Procedures, including both temporary and permanent revision The following categories and procedures were specifically reviewed during this inspection: Startup/Operations/Shutdown of Safety-Related Systems (1)
SOP-6 Reactor Control System (2)
SOP-15 Service Water System (3)
FM-147 Removal from Service of "A" Critical Service Water Header (4)
FM-148 Heade (5)
SOP-16 (6)
FM-111 (7)
FM-112 (8)
SOP-22 (9)
FM-131 (10) FM-132 Return to Service of "A" Critical Service Water Component Cooling Water System Removal from Service of a CCW Heat Exchanger Return to Service of a CCW Heat Exchanger Emergency Diesel Generator Removal of an EDG from Service Return to Service of an EDG from Service Procedure FM-131 appears more restrictive than the technical specification interpretation concerning emergency power to charging pumps discussed in Paragraph 2.a, abov This was discussed with the licensee.
Abnormal/Alarm Condition Procedures (1)
Dl.21 Reactor Protective System (2)
Dl.7 Auxiliary Systems (a)
Service Water System (b)
Component Cooling Water (3)
Dl.20 Diesel Generators 1-1 and 1-2 The alarm procedures section is not now well indexed to permit quick and easy location of required alarm response instruction This was also discussed with licensee personne Administrative Procedures (1)
6.5.4 Surveillance Testing (a)
EM-09-01 Technical Specification Testing (b)
EM-09-02 Inservice Testing of Plant Valves (2) 5.5.1 Maintenance Orders General Plant Operating Procedures (1) A.5.2 Startup from Cold Shutdown to Hot Standby (2)
A.5.11 Recovery from Reactor Trip
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Selected maintenance procedures were also reviewed during this inspection, as identified in Paragraph 4, belo Plant Emergency Procedures will be examined during a future inspection, when the licensee has completed a significant revision process currently underwa No items of noncompliance or deviations were identifie.
Maintenance Procedures and records relating to selected plant maintenance activities were reviewed during this inspection, and two maintenance activities were directly observed by the inspecto As noted above, the Administrative Procedure for Maintenance Orders and several procedures for removal from, or return of equipment to service were examine The following procedures for maintenance were also specifically reviewed: CCS-M-1 Component Cooling Water Pump Disassembly and Reassembly Procedure CRD-M-20 CRDM Bevel Gear Housing Inspection and Rework Procedure EPS-M-2 Corrective Electrical and Mechanical Maintenance for Diesel Generators 1-1 and 1-2 PCS-M-27 Procedure for Testing the Primary Coolant Pump Shaft Seal Cartridge SWS-M-1 Service Water Pump Removal and Inspection Procedure These procedures were considered to provide adequate detail; appropriate administrative and review controls including hold points; and necessary checklist Documentation relating to selected maintenance packages, to verify proper classification, completion by qualified personnel, an adherence to ~dministrative requirements was reviewed for the following maintenance orders: SWS79-003 Repacking of service water pump P-7C SWS79-021 Repair of malfunctioning PCV on service water booster pumps RRS79-001 Reset of auto-withdrawal alarm setpoint to 3°F from 4°F for T f against T re ang
- 6 - CRD 79-015 Repair of unmoveable control rod (#25) EPS79-044 Jumpering of battery cells 32 and 33 following failure EPS79-063 Repair of repetetively tripping breaker on EDG air-compressor motor EPS79-064 Repair of failed gas engine on EDG air-compressor CCS79-003 Installation of test thermocouples and pressure guages on CCW heat exchanger CCS79-005 Adjustment of CCW pump discharge pressure switch auto-start setpoint The inspector also directly observed maintenance work on a control rod drive level gear housing (using CRD-M-20) and a flatness check performed on a primary coolant pump seal as part of the specifications for receipt inspectio Both activities were considered and handled as safety-related jobs and plant Quality Contorl staff members were also present to provide independent review function Qualified personnel were employed, and procedures were present and in use at the jobsite as require No items of noncompliance or deviations were identifie New Fuel Receipt In followup to a previous inspection,~/ the inspector completed his review of activities relating to the receipt of new fuel during this inspection. This review included direct observations of licensee fuel bundle inspection activities for several bundles, and review of documentation regarding receipt activities completed by maintenance, quality control, and health physics staff The inspections observed by the NRC inspector were completed according to procedures, which were present and in use; each bundle being unpacked, visually and mechanically inspected, and stored by the means prescribe A few minor items such as two missing checkmarks and some incomplete notations on "envelope" testing stripcharts, as well as one missing stripchart, were noted during the documentary revie The licensee was aware of these items and will determine which, if any, require correctio One bundle failed the "envelope" test initially but was
"ff IE Inspection Report 50-255/79-1 J
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- .'J straightened by a representative from the fuel manufacturer and subsequently passe The licensee is also determining acceptability for this ite No items of noncompliance or deviations were identifie.
Management Interviews A management interview was held at the completion of the inspection on August 31, 197 Additional meetings to discuss inspection status were held on August 10, 17, and 24, 197 The following matters were specifically discussed at the August 31 meeting: The inspector summarized the scope and findings of this inspectio The interpretation of requirements for emergency power to charging pumps was reviewed, the inspector noting licensee procedures do not currently reflect the technical specf ications as interpreted by the license (Paragraphs 2.a and 3.a) The need for improved indexing to enable quirk location of instructions for control room alarms was discusse (Paragraph 3.b) The licensee expressed an awareness of the essentially permanent nature of selected installed jumpers/bypasses and stated these are occasionally reviewed (though not necessarily on a fixed schedule) for possible processing as facility modification (Paragraph 2.b)
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