IR 05000266/1979019
| ML19305B613 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/25/1980 |
| From: | James Smith, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19305B596 | List: |
| References | |
| 50-266-79-19, 50-301-79-21, NUDOCS 8003190968 | |
| Download: ML19305B613 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/79-19; 50-031/79-21
Docket No. 50-266; 50-301 License No. DPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach Nuclear Power Plant, Units 1 & 2 Inspection At: Point Beach Site, Two Creeks, WI R f w f,,.
Inspector:
J. D. Smith
/-2 J- #p
'RFWA Approved By:
R. F. Warnick, Chief
/- 2 T-A0 e
Reactor Projects Section 2
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Inspection Summary
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Inspection on December 4-7, 14-15 and 18, 1979 (Report No. 50-266/79-19; 50-301/79-21)
Areas Inspected: Routine, unannounced inspection on December 4-7 to review plant operations, procedures, bulletin follow-up, non-routine event follow-up and independent inspection. Announced inspection on December 14-15 and 18 for non-routine event follow-up. The inspection involved 41 inspec-tor-hours by one NRC inspector.
Results: Of the four areas inspected no items of noncompliance were identified.
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. Q DETAILS
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1.
Persons Contacted
- G. A. Reed, Manager, Nuclear Power Division
- J. Greenwood, Assistant to the Manager F. T. Rhodes, Operations Superintendent J. Reisenbuechler, Instrument and Control Engineer T. Ross, Training Supervisor The inspector also talked with and interviewed members of the oper-ations and maintenance section.
- Denotes those attending the exit interview on December 7, 1979.
2.
Plant Operations a.
Plant Tour (1) The inspector performed a plant tour. The housekeeping was good.
(2) Selected valves in the auxiliary feedwater, residual heat removal, and core spray system were checked for proper alignment and no discrepancies were noted.
(3) Shift turnovers were observed to verify continuity was maintained. No discrepancies.were noted.
b.
The jumper bypass logs were reviewed and no discrepancies were noted.
c.
Log Book, log sheets and shift surveillance check records were reviewed for selected days during the past quarter. No items of concern were noted.
d.
Special Orders and Operation Standing Orders The current subject orders were reviewed and no discrepancies were noted.
e.
Manager's Supervisory Staff Meeting Minutes The subject minutes for meetings 79-36 through 79-51 were reviewed. No items of concern were identified.
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3.
Bulletin Follow-up:
The licensee's response to the following bulletins was reviewed to ensure compliance, implementation or consideration as appropriate.
No items of noncompliance or deviations were identified. (Closed)
79-09, Failures of GE Type AK-2 Circuit Breaker in Safety Related Systems 79-10, Requalification Training Program Statistics 79-11, Faulty Overcurrent Trip Device in Circuit Breaker for Engineered Safety Systems 79-15, Deep Draft Pump Deficiencies 79-21, Temperature Effects on Level Measurements 79-23, Potential Failure of Emergency Diesel Generator Field Exciter Transformer 79-24, Frozen Lines l
4.
Reportable Occurrences The following reportable occurrences were reviewed by examination of logs, records, and through discussions with plant personnel.
I Occurrences were reviewed for completion of reporting requirements, compliance with Technical Specifications, investigation and deter-minat'an of cause, proposed corrective measures, and/or completion of corrective action.
a.
RO 50-266/79-13 - Tube Leak in Unit 1 Steam Generator A.
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I Following the return to servic<. on August 18, 1979, the leakage was approximately 150 gallons per day. The leakage rate in-creased gradually to 324 gallons per day by August 29, 1979 when
,the licensee made the decision to shut down for repair. Leak
. testing-revealed one tube to be leaking, and one tube was 88%
-defective. Both tubes were plugged and the unit was returned to service on September 2, 1979.
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R0'50-266/79-14 - The 1-P2B charging pump failed due to a cylin-j der block crack between the No. 2 cylinder and its suction port.
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Pressure' spiking during the compression stroke following hydrogen separation ~during'the-suction stroke'is suspected to have caused theterack. 'The other two charging pumps have had similar failures.
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Discharge dampeners were installed in October 1978 and have;sig-
nificantly reduced the vibration from the discharge stroke.
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stallation of suction stabilizers is planned which should further
extend pump life and reduce maintenance to the system.
c.
RO 50-266/79-15 - While performing a check of containment pres-sure instruments a loose tube fitting was discovered. An invest-igation of other instrument tube fittings revealed no other dis-crepancies, d.
RO 50-266/79-16 - While performing monthly surveillance tests Diesel Generator 3D failed to start. The problem was traced to a faulty governor which was replaced.
c.
RO 50-266/79-17 - Steam generator eddy current testing during refueling revealed 69 defective tubes in the "A" Steam Genera-tors and 62 defective tubes in "B" Steam Generator. Three of the defective tubes were removed for metallurgical examination.
Plugs were welded in the tube sheet holes for those three. The remainder were explosively plugged.
f.
RO 50-266/79-18 - During a special inspection it was discovered that the taping on the containment fan motor leads did not meet construction specifications. As a result the leads were retaped on Unit 1 fan motors and all on Unit 2 except.the "A" fan which is in a high neutron field. Tne Unit 2 "A" fan will be retaped during next refueling.
g.
RO 50-266/79-19 - While filling "A" Steam Generator an inadver-tent dilution occurred due to the three openings in the tube sheet not having plugs welded in place. (See RO 50-266/ 79-17 above). Boron concentration fell below the Technical Specif-ication limit of 1800 ppm to a minimum of 1733 ppm for approx-imately 1 1/2 hours. At no time did the' reactor deviate from the shutdown condition due to the small dilution. This event was a result of an oversight in planning operational evolutions without fully evaluating equipment conditions. The licensee has discussed this thoroughly with all personnel involved in outage evolutions.
In addition, the procedure for filling the steam generators has been revised to provide a final check of plug status prior to filling the steam generator.
h.
R0 50-266/79-20 - While performing an engineering analysis in accordance with IE Bulletin 79-02 it was discovered that an anchor in_the "A" Steam Generator Auxiliary Feedwater Line did not have a design safety factor greater than 2.0.
The anchor was modified and is now fully functional, i.
RO 50-266/79-21 - On December 11, 1979 primary to secondary steam generator leakage on' Unit 1 increased from approximately 55 gallons per day to approximately 250-260 gallons per day.
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An 800 PSI leak test was performed on December 14, 1979. No leaks were noted in the "A" steam generator.
One leaking tube was found in the B steam generator at a point 20 inches below the top of the tube sheet together with drips in one explosive plug and one welded plug. The inspector was dispatched to the site on the date expecting to follow-up on corrective action on these-leaks and to observe. subsequent hydro test and return to-power.
However, though not required by any license conditions, the licensee decided late on December 14, 1979 to initiate an eddy current test program and reinspect all tubes in regions j
where deep crevice tube failures have been found in the past.
The inspector returned to the Region III Office on December 15, 1979.
The leaking tube was mechanically plugged on December 15, 1979, i
and the dripping plugs were weld repaired on December 17, 1979.
The eddy current test program began in the "A" steam generator on December 15, 1979 and in the "B" steam generator on December 18, 1979. Approximately 950 tubes in each steam generator were tested using the latest techniques. An NDT specialist from the office performed an inspection of the eddy current test program on December 18 and 19, 1979. For details of his inspection see Report No's. 50-266/79-14 and 50-301/79-16.
Of the tubes inspected in "A" steam generator, 19 were plugged-
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18 with definable defects and 1 plugged by mistake.
On "B" steam generator 15 tubes were plugged, this included three tubes that had undefinable indications but were plugged as a consecva-tive measure.
The inspector visited the site again on December 18, 1979 for follow-up purposes and to assess progress. No items of concern were identified.
The unit was returned to operation on December 23, 1979.
j.
-RO 50-301/79-07 - With the unit offline and approximately 20%
steam flow, Main Steam Isolation Valve "B" failed to close.
After tapping on operating mechanism partial closure occurred.
The valve was then reopened, the packing loosened, and the valve closed with 20% flow. Experience has shown that this valve, reverse - check type, would have closed properly at high steam flow conditions.
5.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on December 7,1979.
The inspector summarized the scope and finding of the inspection.
The inspector met with plant management on the 15th and 18th also.
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