IR 05000266/1983007
| ML20024D814 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/07/1983 |
| From: | Bob Fitzpatrick, Hague R, Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024D808 | List: |
| References | |
| 50-266-83-07, 50-266-83-7, 50-301-83-07, 50-301-83-7, IEB-83-02, IEB-83-2, NUDOCS 8308080248 | |
| Download: ML20024D814 (6) | |
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s U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-266/83-07(DPRP); 50-301/83-07(DPRP)
Dockets No. 50-266; 50-301 Licenses No. DRP-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach Nuclear Power Plant Units 1 and 2 Inspection At: Point Beach Site-Inspection Conducted: April 1 - May 31, 1983 Y
l l R.1. Hague [6 7/7/f3
.M Inspectors:
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'Fitzp trick 7!7!f3 Date
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'l 7!7/fd Approved By:
I. N. Jackiw, Chief Projects Section 2B Date Inspection Summary Inspection on April 1 - May 31, 1983 (Reports No. 50-266/83-07(DPRP);
50-301/83-07(DPRP))
Areas Inspected: Routine unannounced inspection by resident inspectors of licensee. action on previous in-pection findings; operational safety; mainte-I nance; surveillance; Licensee Event Reports; IE Bulletins; independent inspection; regional requests and refueling activities. The inspection involved a total of:309 inspector-hours onsite by two inspectors including 36 inspector-hours onsite during off-shifts.
Results: No items of noncompliance or deviations were identified.
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s DETAILS 1.
Persons Contacted:
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- J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent
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G.- J. Maxfield, Superintendent - Operations
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J. C. Reisenbuechler, Superintendent - Technical Services W. J. Herrman, Superintendent - Maintenance & Construction
P. J. Skramstad, Superintendent - Chemistry & Health Physics
- R.
E. Link, Superintendent - EQR R. S. Bredvad, Health Physicist
'R. Krukowski, Security Supervisor
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- F.
A. Flentje, Staff Services Supervisor
The inspectors also talked with and interviewed members of the
- Operations, Maintenance, Health Physics, and Instrument and-Control Sections.
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- Denotes personnel attending exit interviews.
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2.
Action on Previous Inspection Findings (CLOSED) Noncompliance (266/83-04-01-(DPRP)): Failure to follow procedure for using time clock to log in and out of containment.
The licensee determined that the procedure was unnecessary and it
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was cancelled.
3.
Operational Safety Verification The inspector observed control room operations, reviewed applicable
logs and conducted discussions with control room operators during the months of April and May, 1983. The inspector verified the oper-
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ability of selected emergency systems, reviewed tagout records and
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verified proper return to service of affected components. Tours of the Unit 2 containment, auxiliary building, and turbine buildings were i
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 inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
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The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls.
During the months of' April and May, 1983, the inspector walked down the accessible portions of the auxiliary feed, containment spray, and safety injection systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
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b These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and adminis-trative procedures.
No items of noncompliance or deviations were identified
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4.
Monthly Maintenance Observation Station maintenance activities of safety related systems and com-were conducted in accordance with approved procedure guides and industry codes or standards and in conformance with technical specifications.
The following items were considered during this review:
limiting conditions for operation were met while components or the 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 acc;omplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemented
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Work requests were reviewed to determine status of out s
maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
Installation of environmentally qualified pressure transmitters a.
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Steam Generator Tube Sleeving.
Installation of additional containment isolation valves.
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Sandblasting and epoxy coating of service water side of
"C" component cooling heat exchanger.
Following completion of maintenance on the Containment Isolation Valves, the inspector verified that these systems had been returned to service properly.
As of the end of this inspection period, sleeve insertion continues on Unit 2 "A" Steam Generator.
primary leak check performed satisfactorily. complete with Steam Generator sleeving is
"A" Steam Generator is considered to be 59% complete.The sleeving of the 5 shifts, or 2 1/2 days, behind critical path. delays have been enco Some minor
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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 adminis-trative procedures.
No items of noncompliance or deviations were identified.
4.
Monthly Maintenance Observation Station maintenance activities of safety related systems and com-ponents listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and 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 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 certified; radiological controls were implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
a.
Installation of environmentally qualified pressure transmitters.
b.
Steam Generator Tube Sleeving.
c.
Installation of additional containment isolation valves.
d.
Sandblasting and epoxy coating of service water side of
"C" component cooling heat exchanger.
Following completion of maintenance on the Containment Isolation Valves, the inspector verified that these systems had been returned to service properly.
As of the end of this inspection period, sleeve insertion continues on Unit 2 "A" Steam Generator. The "B" Steam Generator sleeving is complete with 1500 sleeves in place and an 800 PSI secondary to primary leak check performed satisfactorily. The sleeving of the
"A" Steam Generator is considered to be 59% complete.
Some minor delays have been encountered and the licensee estimates they are 5 shifts, or 2 1/2 days, behind critical path.
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s To date, the total sleeving job for both generators is 89% complete and'the total man-rem expenditure is 46% of the amount estimated for the complete job.
No items of noncompliance or deviations were identified.
5.
Monthly Surveillance Observation The inspector observed technical' specifications required surveil-lance testing on the Unit 2 Nuclear Instrumentation, Unit 1 and 2 Radiation Monitoring Systems, Unit 2 Steam Generator Eddy Current and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting ccaditions 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 activ-ities:
Unit 1 Reactor Protection System Fire Detection System No items of noncompliance or deviations were identified.
6.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine'that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to pre-vent recurrence had been accomplished in accordance with technical specifications.
266-82-010/03L-0 Improper Procedure I.C.P.-2.9 266-82-011/03L-0 Overpower Delta T Setpoint Incorrect
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266-82-022/01T-0 Steam Generator Tube Degradation due to Debris i
266-82-022/-01T-l'
Steam Generator Tube Degradation due to Debris (Update)
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l 266-82-022/01X-2 Steam Generator Tube Degradation due to Debris l
(Update)
266-82-026/01T-0 Failure of NBFD Relays
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266-82-027/03L-0 Steam Generator Pressure Transmitter Sensing Line l
Frozen l
266-83-003/01T-0 Loss of Power to ICV-3200B and Non Essential Load Stripping 301-83-001/03L-0 Boric Acid Heat Tracing Inoperable
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301-83-002/01T-0 Steam Generator Tube Eddy Current Results l
301-83-005/01T-0 Loop A RTD Bypass Valve Degraded Studs l
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No items of noncompliance or deviations were identified.
7.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the Bulletin was received by licensee management and reviewed for its applicability to the facility.
If the Bulletin was applicable 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 presented in the Bulletin and the licensee's response, that the licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information dis-
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cussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written response.
83-02 Stress corrosion cracking in thick wall large-diameter stainless steel, recirculation system piping No items of noncompliance or deviations were identified.
8.
Independent Inspection During the shutdown for the Point Beach Unit 2 refueling outage, higher than normal Iodine-131 levels were noted in the reactor coolant system.
This prompted the licensee to perform visual and sipping inspections of all baffle and optimized fuel assemblies. One of the optimized fuel assemblies (ZD-3) gave positive leakage indications during the sipping inspection. Vendor representatives were contacted and they performed breakaway force measurements, which also indicated anomalies.
The vendor then performed a visual (T.V.) inspection of the removable rodlets, which showed that eight of the rodlets had through wall penetrations at the first gridstrap elevation (lowest support point).
Each rodlet had two areas of throughwall penetrations 90 apart, each area had two penetrations. All of these rodlets had indications of Zircallory Hydriding. Two other non-removable rodlets also had what appeared to be Zircallory Hydriding blisters. Two other removable rodlets showed significant wear in the same pattern as the other rodlets with the throughwall penetrations. The final decision on reese of this assembly has not been reached pending furtner evalua-tions by the licensee and vendor. The other three optimized fuel assemblies showed no anomalies. The licensee has sipped all assemblies being returned to the core with no other abnormal indications.
The licensee also performed visual inspections of the Rod Control Clusters (RCC's). During this inspection most RCC's exhibited signs of fretting in the area of the guide plates. A vendor representative was called in to evaluate this apparent problem. While performing his inspection the vendor representative noted that one of the rodlets on RCC-71 had a two and one quarter inch crack near the end plug.
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The licensee and vendor are still evaluating the data obtained in the above inspections.
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The resident inspectors are following both of the above problems closely.
No items of noncompliance or deviations were identified.
9.
Refueling Activicies
The inspectors verified that prior to the handling of fuel in the core, all surveillance testing required by the technical speci-fications and licensee's procedures had been completed; verified that during the outage the-periodic testing of refueling related
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equipment was performed as required by technical specifications; observed 3 shifts of the fuel handling operations and verified the activities were performed in accordance with the technical specifi-
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cations and approved procedures; verified that containment integrity was maintained as required by technical specifications; verified that good housekeeping was maintained on the refueling area; and, verified
'that staffing during refueling was in accordance with technical speci-fications and approved procedures.
i No items of noncompliance or deviations were identified.
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10.
Regional Request The inspector verified by inspection that the Unit 2 containment pressure sensing lines in containment are open to containment atmosphere. The licensee has utilized pipe caps with holes drilled
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in them which are locked in place with an administrative red lock.
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Placards next to the pipe caps instruct that they are to be in place at all times except during integrated leak rate testing.
11.
Exit Interview The inspector met with licensee representatives (denoted in
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. Paragraph 1) throughout the month and at the conclusion of the inspection period and summarized the scope and findings of the inspection activities. The licensee acknowledged the findings.
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