IR 05000546/1981008
| ML20005B106 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 06/15/1981 |
| From: | Little W, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20005B102 | List: |
| References | |
| 50-546-81-08, 50-546-81-8, 50-547-81-08, 50-547-81-8, NUDOCS 8107060315 | |
| Download: ML20005B106 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPFCTION AND ENFORCEMENT
REGION III
Reports Nos. 50-546/81-08; 50-547/81-08 Docket Nos. 50-546;,50-547 License Nos. CPPR-170; CPPR-171 Licensee:
Public Service of Indiana Post Office Box 190 New Washington, IN 47162 Facility Name: Marble Hill Nuclear Generating Station, Units 1 and 2
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Inspection At: Marble Hill Site Jefferson County, IN Inspection Conducted: May 5-7, 1981 c.e Inspector:
E. R. Schweibinz d-/[
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Approved By:
h.'S. Little, Chief
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Reactor Projects Sect?.an 2C Inspection Summary
!aspection during the period of May 5-7, 1981 (Reports No. 50-546/81-08; 50-547/81-08)
Areas Inspected: Followup on 10 CFR 50.55(e) reportable items. This inspection involved a total of 18 inspector-hours onsite by one NRC inspector, including 0 inspector-hours during off-shifts.
Results: No items of noncompliance or deviations were identified.
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D DETAILS Principal Persons Contacted Public Service of Indiana (PSI)
L. Ramsett, Executive Director - Nuclear Quality Assurance W. M. Petro, Executive Director - Nuclear Project Management
- C. G. Beckham, Quality Engineering Manager
- S. J. Brewer, Nuclear Safety and Licensing Manager
- R. P. Keele, Quality Administration Superintendent
- R. D. Crouch, Quality Verification Records Superintendent
- T. D. Geib, Project Engineer, Nuclear Safety and Licensing
- J. K. Wa t fe, Quality Assurance Administrative Assistant
- Denotes those present at the exit meeting.
The inspecto-
'to contacted and interviewed other licensee and contractor personnel.
Functional or Program Areas Inspected Evaluation of Items Reported per the Requirements of 10 CFR 50.55(e)
(Closed) 10 CFR 50.55(e) reportable item (546/80-01; 547/80-01) Lack of test or equipment to detect failure of Westinghouse permissive P-4 which could lead to loss of safety functions. This item was reputto from the licensee to Region III on January 11, 1980. The licensee's final report on this item, February 7, 1980 was reviewed. In addition, the following licensee correspondence identified by their Document Sequence Numter (DSN) was reviewed:
1126795083, 0128804000, 0111804006, 0129805048, 0204804002, and 0303805023. A Westinghouse letter to the director of IE, February 15, 1980, which contains Revision 1 of the Westinghouse reccom-mended test procedures was also reviewed. This item is closed.
Incorporation of the above recc nanded test procedures prior to fuel load
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l will be reviewed during a future inspection (546/81-08-01; 547/81-08-01).
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(Closed) 10 CFR 50.55(e) reportable item (546/80-02; 547/80-02) Potential for erroneous steam generator water level indication during a high energy
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line break. This item was reported by the licensee to Region III on l
Janua ry 16, 1980. The final report by the licensee dated February 6, 1980 was reviewed. The following correspondence identified by the licensee's DSN was reviewed:
0709794008, 0703790036, 1219795035, 1219795044, 0128804005, 0204804000, and 1210805017. Two letters, one from Westinghouse to the Director of IE dated June 22, 1979, and one from
Westinghouse to the PSI Project Engineering Manager dated December 1, 1980,
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recommend changes to be made to compensate for high level indications.
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This item is closed.
The incorporaticn of the above or other recommendations will be reviewed during a future inspection.
(546/81-08-02; 547/81-08-02)
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.(Closed) 10 CFR 50.55(e) (546/80-03; 547/80-03) Non-conservative rod drop
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analysis by Westinghouse. This item was reported by the licensee to Region III on January 1, 1980. The final report dated February 7,1980 was reviewed. The following licensee correspondence identified by DSN was reviewed:
1128795032, 0128804005, 0129805047, and 0208804003. The licensee har committed to incorporate the appropriate long term solutions that will be identified by Westinghouse in a topical report to be submitted to NRC. This item is closed.
The incorporation of the Westinghouse recommened long term solutions will be reviewed during a future inspection.
(546/81-08-03; 547/81-08-03)
(Closed) 10 CFR 50.55(e) reportable item (546/80-07; 547/80-07) Reduced steam generator cooling during feed water line break due to failure in steam generator blowdown system. The licensee reported this item to Region III on February 22, 1980. The interm report dated March 19, 1980 was reviewed. The licensee determined this item to not meet the report-ablity requirements in their final report dated May 13, 1980. The final report included an accident analysis as an attachment. This analysis was reviewed and found to be acceptable. The following licensee correspondence identified by DSN was also reviewed: 0227805069, 0320804003, 0320804004, 0421805032, 0506814003, 0529804001, and 0511815013. The RIII inspector was unable to determine through a review of the correspondence available that Sargent & Lundy had used the Westinghouse procedures which were transmitted in their April 11, 1980 letter to Public Service of Indiana
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(PBW-1885).
The licensee obtained a ccafirmation that these procedures were used during this 1.*'ection.
Thir item Js documented in a May 7, 1981 letter to PSI Proje. Director. Tnis itea is closed.
(Closed) 10 CFR 50.55(e) (546/80-13; 547/80-13) Review of Westinghouse quality verification packages performed under SPP-7 had indicated 46 noncomformances out of the sample size of 49 document packages. This item was reported by the licensee to Region III on July 7, 1980. An interm report dated July 30, 1980 was reviewed. This item was retracted in a final report dated October 17, 1980. The following licensee correspondence indicated by DSN was reviewed: 0707804018, 0709804003, 0723804006, 0725806514, 0507814015, 0918804005, 0909806506, and 1113804020.
In addition, an August 29, 1980 memo from Berlin to Juvic was reviewed.
The actions taken were found to be acceptable and this item is closed.
Exit Meeting The inspector met with site staff representatives (denoted in The Persons Contacted paragraph) on May 7, 1981. The inspector summarized the scope and findings of the inspection.
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