IR 05000295/1985018
| ML20127E786 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/05/1985 |
| From: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| 50-295-85-18, 50-304-85-19, NUDOCS 8506240653 | |
| Download: ML20127E786 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-295/85018(DRP); 50-304/85019(DRP)
Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee: Cocoonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Zion Nuclear Power Station, Units 1 and 2 Inspection At: Zion, IL Inspection Conducted: April 30 through May 29, 1985 Inspectors:
M. M. Holzmer L. E. Kanter J. N. Kish
l Approved By: G.C.Wrigd*, Chief b!f f Reactor Projects Section 2A Date Inspection Summary Inspection on April 30 through May 29, 1985 (Reports No. 50-295/85018(DRP);
50-304/85019(DRP))
Areas Inspected: Routine, unannounced resident inspection of licensee action on previous inspection findings; operational safety and ESF walkdown; surveillance; maintenance; LER's; and followup of Region III requests.
The inspection involved a total of 214 inspector-hours onsite including 54 inspector-hours onsite during offshifts.
Results: Of the six areas inspected, no violations or deviations were identified in five areas, and one violation was identified in the remaining area (Failure to submit an LER within 30 days per 10 CFR 50.73-paragraph 7).
8506240653 850605 PDR ADOCK 05000295 O
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DETAILS 1.
Persons Contacted
- K. Graesser, Station Manager E. Fuerst, Assistant Superintendent, Operations
- G. P11ml, Superintendent, Production Support Services t
- K. Kofron, Assistant Superintendent, Maintenance R. Budowle, Unit 1 Operating Engineer
- J. Gilmore, Unit 2 Operating Engineer L. Pruett, Rad Waste Operating Engineer M. Carnahan, Training Supervisor
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- W. Kurth, Assistant Superintendent A. Ockert, Assistant Technical Staff Supervisor C. Schultz, Assistant Technical Staff Supervisor
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T. Rieck, Superintendent, Services
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- J. Ballard, Quality Control Supervisor D. Kaley, Quality Control Engineer W. Stone, Quality Assurance Supervisor
- D. McHenamin, Quality Assurance Engineer
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R. Cascarano, Technical Staff Supervisor
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G. Trzyna, Rad Chem Supervisor i
E. Campbell, Master Instrument Mechanic
- A. Bless, Licensing Staff
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- Indicates persons present at exit interview.
2.
Licensee Actions On Previous Inspection Findings
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(Closed) Noncompliance (295/84-23-01) Failure of Diesel Generator (DG)
maintenance procedures to include fill and vent operations prior to return to service. The licensee has revised procedure DG001/3-4,
" Closeup of a Diesel Generator Power Cylinder" to include steps to fill
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and vent the DG jacket water cooling pump. Surveillance procedure PT-11,
" Diesel Generator Surveillance Test" was also revised to add a note for
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operators to check the DG jacket water expansion tank for the expected slight drop in level when starting the engine.
(Closed) Noncompliance (295/84-12-02; 304/84-12-04) Failure to approve
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instrument mechanic special procedures (IMSP's) prior to use. All safety-related IMSP's have been superseded by properly reviewed and approved instrument maintenance procedures.
J (0 pen) Noncompliance (304/84-12-05) Failure to accomplish activities
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affecting quality under suitably controlled conditions. While in the process of revising IM procedures the licensee took additional steps to incorporate independent verification requirements in response to NRC inspection report 295/84-21; 304/84-22.~ The addition of these steps added considerable complexity to several procedures. As' a result, the entire system of IM procedures will be overhauled.
The licensee expects to
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complete these revisions by August 1, 1985. This item wf11 remain open
pending review of the licensee's corrective actions.
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(0 pen) Open Item (304/85013-02) Unit 2 reactor trip during ground isolation activities.
The licensee's investigation is complete.
This item will remain open pending the review of procedure ZED-3, (ground checking procedure). LERs 304/85-08 and 304/85-08-01 were issued by the licensee covering this event (see paragraph 7).
No violations or deviations were identified.
3.
Summary Of Operations Unit I remaining in cold shutdown undergoing a refueling outage for the duration of inspection period.
Unit 2 operated at power levels up to 100 percent throughout the inspection period. On April 30 and May 22, 1985, power was reduced to 50 percent to allow for the filling of 28 and 2D RCP oil reservoirs respectively. On May 6,1985 the No. 4 governor valve and stop valve were closed and power level ramped down to 95 percent due to the possibility of exceeding a 100 percent power level due to governor valve oscillations. The cause of the oscillations is under investigation.
The unit is continuing to operate with the valve closed.
4.
Operational Safety Verification and Engineered Safety Features System Walkdown The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators from April 30, 1985 through May 29, 1985. During these discussions and observations, the inspectors ascertained that the operators were alert, fully cognizant of plant conditions, attentive to changes in those conditions, and took prompt action when appropriate. The inspectors verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components.
Tours of the auxiliary and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspectors by observation and direct interview verified that the physical security activities were being implemented in accordance with the station security plan.
The inspectors observed plant housekeeping / cleanliness conditions
~ and verified implementation of radiation protection controls. From April 30, 1985 to May 29, 1985, the. inspectors walked down the accessible portions of the auxiliary feedwater, component cooling, service water penetration pressurization, and isolation valve seal water systems to verify operability. The inspectors 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 procedures.
No violations or deviations were identified.
5.
Monthly Surveillance Observation The inspector observed Technical Specifications required surveillance testing on the fire protection, containment spray, and safeguards systems 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 during the testing were properly reviewed and resolved by appropriate management personnel.
The inspector also witnessed portions of the following test activities:
PT-6 Containment Spray Tests and checks PT-10 Safeguards Actuation Test PT-205 Transformer Deluge System Test No items of noncompliance or deviations were identified.
6.
Monthly Maintenance Observation Station maintenance activities on safety-related systems and componen3 listed below were observed or reviewed to ascertain whether they were conducted in accordance with approved procedures, regulatory guides industry codes or standards and in conformance with Technical Specifications.
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 calibration; were perfomed 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 certified; radiological controls were implemented; and fire prevention controls were implemented.
Work requests were reviewed to detennine status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may affect system performance.
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The following maintenance activities were observed or reviewed:
1A Charging Pump Maintenance IB Charging Pump' Room Cooler Repair IA Service Water Strainer Replaement Omega Seal Weld for Control Rod Drive H-10 Relief Valve Testing
Following completion of maintenance on these components the inspector i
verified that these systems had been returned to service properly.
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Preventive maintenance activities were reviewed during the inspection.
The ifcensee's preventive maintenance (PM) program was formally
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established in June, 1984. Until that time, PMs were done at the discretion of each work group. PMs are now scheduled as part of a master schedule which is entered on a computer.. Monthly lists of PMs
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are generated and issued to mechanical and electrical maintenance, and
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the PM group is represented at the weekly TJM (Total Job Manual) meetings.
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The effectiveness of the PM program is difficult to measure at this point,
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since the backlog of work requests resulting from the Unit 1 outage has made it difficult to perform PMs on schedule.
The licensee will be making use of its data processing capabilities to make machinery history more useable. This should allow the work analysts to assemble work l
packages more efficiently.
These work packages have begun to include
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PMs which are coming due in the near future.
In addition, mechanical maintenarce is also taking credit for corrective maintenance activities
which satisfies PM requirements.
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No violations or deviations were identified.
7.
Licesee Event Reports (LER) Followup
Through direct observations, discussions with licensee personnel, and
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review of records, the following event reports were reviewed to detennine i
that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specifications.
The LERs listed below are considered closed:
UNIT 1
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j LER N0.
DESCRIPTION j
85-12 Improper Pressure Used For Fire Hose Surveillance
Testing 85-12-01 Improper Pressure Used For Fire Hose Surviellance
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Testing (Revision)
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85-13 RCS Boron Dilution Event During Shutdown i
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UNIT 2 t
LER NO.
DESCRIPTION 85-08 Reactor Trip During Ground Isolation Activities
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85-08-01 Reactor Trip During Ground Isolation Activities
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(Revision)
85-09 Failure To Withdraw Capsule X For Reactor Vessel f
Surveillance 85-11 NHC Radiation Monitors Inoperable Due To Loss Of
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84-32 Reactor Trip On OP Delta T While Removing RTD Test Cart
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Regarding LER 295/85-12-01, this item was identified during a corporate Quality Assurance inspection, and corrective action has
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been initiated to test station fire ~ hoses at the required pressure.
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This is a licensee identified violation for which no citation will j
be given (295/85018-01;304/85019-01).
The ifcensee expects to complete
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the testing of station fire hoses during the surnner. This action is i
designated an Open Item pending review of the completed fire hose i
hydro testing (295/85018-02;304/85019-02).
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i Regarding LER 295/85-13, the licensee will submit an updated LER to correct two valve numbers.
This matter is designated an Open Item
a pen fing review of the updated LER and of the Ifcensee's corrective
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acteons(295/85018-03).
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Regarding LER 304/85-09, this item was identified during the preparation
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j of a revision to the licensee's Technical Specifications.
Because of
.i the low leakage core loading patterns, the revised date for withdrawal.of capsule-X will be in 1987. This is designated a licensee identified
violation for which no citation will be given (304/85019-03).
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Regarding LER 304/84-32, the Deviation Report (DVR) which would have initiated the LER was inadvertently filed in the startup package,
following the_ reactor trip, prior to being entered into the DVR tracking
system. As a result, there was no record of the DVR at the station.
The item was identified when NRC headquarters offices questioned whether-
an LER was issued (headquarters was notified of the trip pursuant to
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10 CFR 50.72 on July 5, 1984). Failure to submit an required LER l
within 30 days'is a violation of 10 CFR 50.73 (304/85019-04).
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No violations for late LERs have been issued since October'1984.
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i addition, the licensee has issued a station procedure covering DVR j.
handling. As a result, no response to this violation is~ required.
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l No other violations or deviations were. identified.
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8.
Followup of Region III Requests i
TI 2515/54 - Near Term Inspection Followup To Generic Letter 83-28 (Salem
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ATWS)
In a memorandum from C. E. Norelius dated March 27, 1985, all resident i
inspector offices.were directed to provide infonnation concerning the ifcensee's response to Generic Letter 83-28 to the Regional Office
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Program Coordinator for G.L. 83-28. The resident inspectors assembled a
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package containing 20 safety-related work requests covering the reactor
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trip system, containment spray and residual heat removal systems.
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addition, the inspectors provided a copy of the licensee's program for
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reactor trip breaker maintenance.
These materials were delivered to the regional office on May 7, 1985.
Auxiliary Feedwater Pump Steam Binding In a memorandum from C. E. Norelius dated April 18, 1985, all resident inspectors were requested to conduct an inspection of their respective station's methods to detect and avoid steam binding of the auxiliary i
feedwater pumps.
In accordance with the above request the inspectors
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l reviewed auxiliary building daily log sheets, inspected the auxiliary feedwater pumps and conducted interviews with the nuclear station i
i operators and equipment attendants (EAs).
The licensee monitors the temperature of the pump casings every shift locally by touch.
Training j
is provided to alert the EAs of the possibility of steam binding.
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No violations or deviations were identified.
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Open Items
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Open Items are matters which have been discussed with the licensee which
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will be reviewed further by the inspector and which involve some action i
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Two Open Items disclosed
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j during this inspection are discussed in paragraph 7.
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Exit Interview
i The inspectors met with ifcensee representatives (denoted in Paragraph 1)
i throughout the inspection period and at the conclusion of the inspection
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l on May 29, 1985. to sumarize the scope and findings of the inspection
activities. The licensee acknowledged the inspectors' comments.
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inspector also discussed the likely infonnational content of the
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inspection report with regard to documents or processes reviewed by the inspector. during the inspection. The ifcensee did not identify any such documents-or processes as proprietary.
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