IR 05000546/1979019
| ML19262A896 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 10/18/1979 |
| From: | Harrison J, Hawkins F, Hayes D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262A885 | List: |
| References | |
| 50-546-79-19, 50-547-79-19, NUDOCS 7912110286 | |
| Download: ML19262A896 (5) | |
Text
{{#Wiki_filter:. . U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-546/79-19; 50-547/79-19 s Docket No. 50-546; 50-547 License No. CPPR-170; CPPR-171 Licensee: Public Service of Indiana 1009 East Main Street Pl infield, IN 46168 Facility Name: Marble Hill Generating Station, Units 1 and 2 Inspection At: Marble Hill Site, Jefferson County, Indiana Inspection Conducted: September 25-28 and October 9-12, 1979 ; - -3 . , Inspector: F. C. Hawkins / ' -,,.a , Accompanying Personnel: C.
C'. Williams (September 25-28 and October 12, 1979) [[*,%,, r{ a s n.
. p J. J. Harrison (October 12, 1979) j (- . .i y ' Approved By: D. W. Hayes, Chief , Engineering Support Section 1 Inspection Summary Inspection on September 25-28 and October 9-12, 1979 (Report No. 50-546/79-19; 50-547/79-19) Areas Inspected: Observation of concrete coring work and review of related quality records; observation of maintenance for installed Category I material; observation of work related to the off-loading of the Unit 2 Reactor Pressure Vessel.
Results: No items of noncompliance or deviations were identified.
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. DETAILS Persons Contacted Public Service of Indiana (PSI)
- L.
Crews, Vice President, Construction
- W. L Ward, Construction Manager
'
- R. E. Woolley, Construction Supervisor. Engineering
,
- M. Morris, QC Manager
- W. A. Muensterman, Senior Construction Supervisor F. R. Hodges, QA Manager
- T. L. McLarty, QA Construction Supervisor S. K. Farlow, Site Design Control Supervisor D. L. Shuter, QC Engineer G. Weston, QC Engineer Newberg Construction Company T. L. Kueck, Area Superintendent D. Coker, Area Superintendent J. Ball, QC Engineer M. Rose, QC Engineer Other Personnel A. Weiss, Concrete Technologist, S&L K. Seeber, Site Design Control Engineer, S&L J. D. McKoughlin, National Board of Boiler and Pressure Vessel Inspectors J. G. Gillissie, National Board of Boiler and Pressure Vessel Inspectors R. Beckwith, National Board of Bciler and Pressure Vessel Inspectors R. R. Johnson, State of Indiana Boiler and Pressure Vessel Board Congressional Representatives J. R. Galloway, Staff Director Subcommittee on Environment, Energy and National Resources R. C. Brown, Counsel Subcommittee on Environment, Energy and NE ional Resources
- Denotes those present at the exit interview.
Functional or Program Areas Inspected Details of functional or program areas inspected are documented in the following paragraphs.
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1.
Concrete Coring Based on the results of the nondestructive tests performed by the Construction Technology Laboratories, eight areas (No. 17, 23, 30, 35, 36, 51, 53 and 60) which contained discontinuitiet not attrib-utable to the presence of congested reinforcing steel, embedded items or structural steel or structural steel supports for embedded items were chosen to be examined by destructive testing (i.e. coring). Two areas (No. 9, 28) in which discontinuities were attributed to various embedded ' items were aiso selected to be cored. These ten areas are part of the , 54 Category T and six Category II areas selected for nondestructive examination in the Unit No. 1 Reactor, Auxiliary and Turbine Buildings.
In addition, one extra core each, from Areas No. 22, 23, 25, 26 and 27 were taken. These five additional cores were located in areas where mechanical penetrations were omitted during construction. The purpose of these five destructive tests was to verify that the nondestructive tests were indicative of the in place concrete. The following specific observations were made.
- The inspector confirmtd that G. K. Newberg (N-MH) procedure WPN-22, Revision 1, dated January 31, 1978, entitled Concrete Coring had been reviewed and approved by the appropriate authorities prior to commencement of work.
- The inspector reviewed the experience record of the Atec Associates driller and the qualifications of the N-MH Drilling Superintendent.
The Drilling Superintendent's records were in accordance with N-MH QAPN-3, as required by WPN-22, Revision 1.
- The following is a list of area numbeis, locations and the length - of the core taken from each.
Area No.
Location Length (inches)
Auxiliary Building 32.5
Unit 1 Reactor Building
22* Auxiliar," Building
23 Auxiliary Building 22.5 23* Auxiliary Building
25* Auxiliary Building
26* Auxiliary Building 40.25 27* Auxiliary Building
28 Auxiliary Building
30 Auxiliary Building
35 Auxiliary Building
36 Auxiliary Building 28.5
Auxiliary Building
53 Unit 1 Reactor Building 28.5
Turbine Building
- Cores taken to verify nondestructive test results.
\\ -3-
. . No items of noncompliance were identified.
2.
Maintenance of Installed Category I Material The inspector toured the Unit 1 & 2 Reactor Buildings and observed that the tendon bearing plates and associated hardware in both the Unit 1 & 2 tendon galleries are beginning to show signs of corrosion as a result of their present storage environment.
Licensee personnel ' stated that clean-up of the tendon galleries will be promptly initiated - to facilitate the commencement by October 19, 1979 of preventive maintenance work on the bearing plates and trumpets.
The proposed PSI plan for action necessary to assure proper mainten-ance of these installed items will be verbally submitted to the NRC RIII office.
In addition, numerous construction openir.gs in the Unit 1 Reactor Building fill slab were observed to be full of water, thus exposing the installed reinforcing steel to unfavorable storage conditions.
The licensee stated that all similar conditions present in the Unit I and 2 Reactor Buildings would be promptly corrected and suitably maintained.
Satisfactory completion of these committments will be confirmed during a subsequent inspection.
(546/79-19-01; 547/79-19-01) No items of noncompliance were identified.
3.
Lifting and Handling of Unit II Reactor Pressure Vessel (Reference RIII Report No. 50-546/79-20: 50-547/79-20) On September 26, 1979, NRC inspector witnessed the lifting and handling of the Unit II Reactor pressure vessel. The vessel was removed from the railway car which transported it to the site and placed in site storage. This operation was conducted in full con-formance to the licensee's procedure number QCX-22 "off-loading reactor pressure vessel." The vessel supplier's (Westinghouse) representatives observed and participated in this operation.
No items of noncompliance were identified.
4.
Site Storage of Unit 1 and 2 Reactor Vessels and Steam Generators Observation of the Unit I and 2 Reactor Vessels and Steam Generators disclosed that in a number of areas on each vessel, degradation of the nrotective coatings has occurred. This was brought to the attention of the site Westinghouse representative and the PSI site construction management. A full assessment of the condition of the protective coatings is to be made and appropriate corrective actions })28 012-4- .
. are to be expedited. This matter is unresolved and will be examinea
during future inspections.
(546/79-19-02; 547/79-19-02) No items of noncompliance were identified.
5.
National Board of Boiier and Pressure Vessel Inspectors Inspection On October 12, 1979, NRC inspectors were present during the National ' Board's exit interview conducted at the close of a three week inspec-tion of those issues identified in the " National Board.
" previous .. . report dated July 10, 1979.
The " National Board.
." indicated that numerous nonconformances had been identified, and the details of these findings would be transmitted to the licensee in a documented report.
The " Board" further indicated that they are considering recommending that plant construction under an ASME " Interim Letter" not be granted.
This matter is considered unresolved and will be examin :d during subsequent inspections.
(546/79-19-03; 547/79-19-03) No items of noncompliance were identified.
6.
Congressional Representatives _ On October 12, 1979, two members of the subcommittee on Environtr.- ., Energy, and National Resources conducted interviews with PSI manage-ment personnel and observed site construction. NRC inspectors were present during this visit to the site.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of r.oncompli-ance, or deviations. Unresolved items disclosed during the inspection are discussed in the Details Section, Paragraphs 4 and 5.
Exit Meeting The inspector met with site staff personnel (denoted in the Persons Contacted paragraph) at the conclusion of the inspections on September 28 and October 12, 1979. The inspector summarized the scope a.id findings of the inspection.
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