IR 05000400/1986063
| ML18019B125 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/18/1986 |
| From: | Blake J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019B124 | List: |
| References | |
| 50-400-86-63, IEB-78-12, NUDOCS 8609030384 | |
| Download: ML18019B125 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MAR I ETTA ST R E ET, N.W.
ATLANTA,GEORGIA 30323
Report No.:
50-400/86-63 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris 1, Inspection Conducted:
July 28 - August 1, 1986 Inspector:
R.
W.
som Approved by:
J. J.
e,
>e Materials Processes Section Division of Reactor Safety SUMMARY License No.:
CPPR-158 Date S gne D
eS ne Scope:
This routine, unannounced inspection was conducted in the areas of licensee action on previous enforcement matters, licensee identified items, inspector identified items, IE Bulletin 78-12, general observation of construction activities, general housekeeping, and material storage'.
Results:
No violations or deviations were identified.
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REPORT DETAILS'
1.
Persons Contacted Licensee Employees
- G. L. Forehand, Director, Quality Assurance/Quality Control (QA/QC),
Construction
- C. L. McKenzie, Acting Director, QA/QC, Operations
- C. S. Hinnant, Manager, Startup
- D. Tibbitts, Acting Director, Regulatory Compliance M. G. Wallace, Specialist, Regulatory Compliance Other licensee employees contacted included construction craftsmen, engineers, technicians, mechanics, security force members, and office personnel.
NRC Resident Inspectors
- G. Maxwell, Senior Resident Inspector S. Burris, Resident Inspector
+Attended exit interview 2.
Exit Interview The inspection scope and findings were sumnarized on August 1, 1986, with those persons indicated in the above paragraph.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (30703)
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(Closed)
Unresolved Item 50-400/85-48-02, Power Wire Brushing Prior to Surface Examinations.
This item concerned liquid penetrant inspection procedure IST-401 which allowed power wire brushing as a method of preparing the examination surface.
This method may, in some cases, cause small flaws to be smeared closed and become undetectable with liquid penetrant examination.
The procedure has been revised and no longer allows the use of power wire brushing for the preparation of surfaces prior to liquid penetrant examination.
The inspector has no further questions regarding this item and considers it close I4
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(Closed)
Unresolved Item 50-400/84-44-05, Program for Inspection of Activities Affecting equality.
This item was written to address the findings of the Construction Appraisal Team (CAT) inspection in NRC Report 50-400/84-41 Appendix B, paragraph 5.b.(2).
Four findings were addressed as being deficient and these items are addressed below.
(1)
Various components within piping systems were installed without accompanying washers at the foundation anchor bolt attachment.
Also, an FCR had been written against the Boric Acid Tank which changed the anchor configuration from double nut to single nut arrangement but did not eliminate the use of washers.
The inspector reviewed the licensee's generic Nonconformance Report (NCR)
No.
85-0901 which was applicable to all safety-related seismic category I designed equipment.
The primary reason for not installing washers as necessary stemmed from a misinterpretation of a typical note relative to the use of washers on bolt attach-ments.
Special training was conducted to clarify the intent of the general note involved.
The inspector reviewed documentation of washer installations and conducted field verifications of selected components as listed below.
COMPONENT TAG NO CVCS Charging Pump Service Water Booster Pump Component Cooling Water Pump Component Cooling Water Pump Fuel Pool Strainer Seal Water Return Filter Seal Water Injection Filter Seal Water Injection Filter Reactor Coolant Filter Component Cooling Heat Exchanger Boric Acid Tank 1C-SAB 1A-SA 1A-SA 1C-SAB 3SF-S4SB 1 5 4 1X-SN 1A-SN 1B-SN 1X-SN 1A-SA 1X-SN The inspector has no further questions regarding this matter.
(2)
The Service Water Booster Pump (1A-SA) did not have documentation that indicated its foundation bolting was torqued to the required value specified by the vendor drawing.
The licensee issued NCR No.
85-0660 requiring the bolting be torqued to its required value and conducted special training for the mechanical equipment inspectors to emphasize the need to review any special requirements relative to component installation.
It should be noted that this item was detected during the Phase II portion of construction and the final Phase III fastener connections inspection had not been conducted at this point.
The licensee indicated that the Phase III inspec-tion was an additional checkpoint and that the condition would
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probably have been identified at that time.
The inspector reviewed documentation relative to the proper tightening of the bolting and has no further questions regarding this matter.
(3)
Grout was found in and around the slotted sections of the base plates on the Diesel Generator Exhaust Silencers.
These sections were designed to be clear to allow movement caused by thermal expansion.
NCR 85-0661 was issued which required the grout to be bush-hammered to correct elevation and the resulting surface was cosmetically repaired.
A procedure change notice was issued to procedure TP-28 that now requires the equipment setting discipline engineer be contacted for, specific grouting directions when equipment is to be grouted.
The inspector reviewed associated documentation and the procedure involved and has no further questions regarding this matter.
(4)
The sliding end of a
CVCS Seat Mater Heat Exchanger exhibited a tight foundation anchor configuration.
The washers between the nuts and the slotted base plates could not be rotated or moved.
Also, the degree of tightness could not be determined.
Yendor instructions for placement, torquing, and locking of nuts at the sliding end of thermally expanding heat exchangers indicated the sliding end should be "lightly tightened".
Field Change Request (FCR)
M-750 was issued by the licensee, after discussions with Westinghouse Electric engineers, and now gives specific torque requirements for the free end of heat exchangers.
The inspector has reviewed the documentation and the FCR which relate to this item and has no further questions regarding this matter.
4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Independent Inspection Effort (54834B)
(42940B)
The inspector conducted a
general inspection of the turbine building, auxiliary buildings, fabrication areas, and storage areas to observe general housekeeping, material storage, and construction activities such as welding.
The inspector did not observe any questionable workmanship and, in general, material. protection, handling, and storage appeared adequate.
Within the areas examined, no violations or deviations were identifie h tf
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6.
Licensee Identified Items (92700)
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(Closed)
Item CDR 84-162, Fire Barriers Tack Welds.
On February 13, 1984, the licensee notified Region II of a 50.55(e)
item concerning broken tack welds on some fire barrier bottom panels that are located above safety-related electrical cable and equipment.~
The final report, submitted on July 1, 1986, has been reviewed and determined to be acceptable by Region II.
The inspector held discussions with responsible licensee and/or contractor representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
This matter is considered closed.
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(Closed)
Item CDR 84-183, Potential Over Pressurization of the Component Cooling Water System.
On August 13, 1984, the licensee notified Region II of a 50.55(e)
i'tern concerning the design of the component cooling water system which could result in an overpressure condition from closure of the surge tank vent valve if a high radiation signal from associated radiation detectors within the system are activated.
The final report was submitted on September 20, 1985.
The report has been reviewed and determined to be acceptable by Region II.
The inspector held discussions with responsible licensee and/or contractor representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
This matter is considered closed.
(Closed)
Item CDR 85-219, Emergency Service Water Pump Material~
Failure.
On November 8, 1985, the licensee notified Region II of a 50.55(e)
item concerning the 1A pump shaft breaking at the upper bearing of the pump.
Bearings and shaft sleeves were destroyed.
In addition, inspection of 1B pump also indicated deterioration.
The final report was submitted on May 12, 1986.
The report has been reviewed and determined to be acceptable by Region II.
The inspector held discussions with responsible licensee and/or contractor representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
This matter is considered closed.
(Closed)
Item CDR 86-227, Main Feedwater Isolation Valves On March 20, 1986, the licensee notified Region II of a 50.55(e)
item concerning main feedwater isolation valve operator piston rod failures on valves 2FW-V28SAB-1 and 2FW-V27SAB-1.
The final report was
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The report has been reviewed and determined to be acceptable by Region II.
The inspector held discussions with responsible licensee and/or contractor representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
This matter is considered closed.
e.
(Closed)
Item CDR 86-229, Emergency Service Water Intake Structure Wall Penetration Seal Type B-2.
On June 9, 1986, the licensee notified Region II of a 50.55(e)
item concerning failure of the penetration seal at the emergency service water intake structure in bay 8 which allowed sand to enter the bay.
The final report was submitted on July 7, 1986.
The report has been reviewed and determined to be acceptable by Region II.
The inspector held discussions with responsible licensee and/or contractor representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
This matter is considered closed.
7.
Inspection and Enforcement Bulletins (IEB) (92703B)
(Closed)
IEB 78-12:
Atypical Weld Material in Reactor Pressure Vessel Welds.
This IEB required the licensee to have a records search conducted for all primary reactor pressure vessel weldments in order to determine if the principal vessel manufacturer might have used incorrect weld material during the fabrication of the vessel.
The records search was conducted by Chicago Bridge and Iron Company, the vessel manufacturer, with Westinghouse Electric reviewing and confirming the records review findings.
Based on all evidence presented, no Atypical weld material was used in the Harris Unit 1 vessel.
The inspector has reviewed portions of the records submitted to substantiate the finding and is in agreement with those findings.
This IEB is considered closed.
8.
Inspector Followup Items (IFI) (92701B)
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(Closed) IFI 50-400/83-27-01, Unavailable Steam Generator Records This item concerned records of fabrication inspection and material certification documentation for steam generators A, B, and C which had not yet been received on site and, therefore, unavailable for review at the time this item was written. The documentation has been sent to the site and has been reviewed, on a selective basis, by the inspector.
This item is considered close w v ~
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(Closed)
IFI 50-400/86-41-01, Spent Fuel Rack Fabrication Records.
This item concerned the review of spent fuel rack records which were not available for review at the time this item was written.
The unavailable records were material certifications for the BWR ad PWR spent fuel racks.
The records are now on site and the following material records were selected for review by the inspector.
PWR BWR Wrapper Cell Retainer Pad Screw-Wrapper Weld Wire Lock Washer Nut Screw Plate The inspector has no further questions regarding this item.'
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