IR 05000546/1981015
| ML20031C593 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 09/21/1981 |
| From: | Little W, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20031C581 | List: |
| References | |
| 50-546-81-15, 50-547-81-15, NUDOCS 8110070330 | |
| Download: ML20031C593 (4) | |
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D U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-546/81-15; 50-547/81-15 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 & 2 Inspection At: Marble Hill Site Jefferson County, IN Inspection Conducted:
September 2-1, 1981 ( S.
Inspector:
E. R. Schweibinz 09@l4(
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h Approved By:
W. S. L ttle, Chief
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Reactor Projects Section 2C
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Inspection Summary
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Inspection during the period of September 2-3, 1981 (Reports No. 50-546-81-15; 50-547/81-15)
Areas Inspected: Followup on 10 CFR 50.55(e) reportable items, Bulletins, Circulars and licensee actions on previous inspection findings. This inspection involved a total of 15 inspector-hours onsite by one NRC inspector, including three inspector-hours onsite during off shifts.
Re_sults: No items of noncompliance or deviations were identified.
8110070330 810U2 PDR ADOCK 05000546
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o DETAILS 1.
Principal Persons Contacted Public Service of Indiana (PSI)
- L. O. Ramsett, Executive Director, Nuclear Quality Assurance
- C. G. Beckham, Quality Engineering Manager
- S. J. Brewer, Nuclear Safety & Licensing Manager R. P. Keele, Quality Administration Superintendent
- T. R. Burns, Project Engineering Manager
- L. G. Yeager, Licensing Engineer T. D. Geib, Project Engineer, Nuclear Safety & Licensing
- J. K. Wolfe, Quality Assurance Administrative Assistant
- Denotes those present at the exit meeting The inspector also contacted and interviewed other licensee and contractor personnel.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (546/79-15-01; 547/79-15-01) Cherne and Chicago Bridge and Iron (CB&I). Questionable method used for final washing of radiographic film. The resolution and closcout of the following documents were reviewed and found to be acceptable.
PSI Field Corrective Action Report FCAR No. 738. dated February 28, 1979; Cherne Nonconformance Rep 3rt NCR 6.77, dated June 5,1979; and CB&I Field Nonconformance Report FNR No. 115, dated February 21, 1979. Th?.s item ie closed.
(Closed) Item of Noncompliance (546/79-18-03; 547/79-18-03) Improper review of design changes-NCR, DCR, ICAR, FCAR, and FNR. A complete review of all noncomformance documents prepared prior to August 16, (
1979, was accomplished through special process procedure SPP-23 titled,
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" Verification of the NCR Review Committees Review Documentation and Current NCR Status." The NRC review and acceptance of SPP-23 is
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l documented in IE Inspection Report No. 50-546/80-37.
At the present time nonconformance reports are controlled by project management
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procedure PMP 3.28, titled " Administration of Noncomformance Reports,"
revision 2, 08-12-81.
The licensee has also used special process procedure SPP-19, titled, " Processing Nonconformances Issued Prior
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l to May 1, 1980", revision 3, 11-19-80 for control of the processing
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of nonconformances. The licensee is currently using special process procedure SPP-27, titled, " Review of NCR's Issued after May 1,1930
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for Proper Justification", Revision 0, 08-05-81.
This item is closed.
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(Closed) Unresolved Item (546/79-18-04; 547/79-18-04) Procedural discrepancies for requirements of design change review. The actions taken by the licensee with regard to the item of noncompliance stated
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above (546/79-18-03) provide an a(equate basis for the resolution of this item.
This item is closed.
(C1csed) Unresolved Item (546/80-32-01; 547/80-32-01) Resolution of UCR C-009-79 with regard to previous item no. 546/79-03-02. The resolution to the design change request which was dispositioned on 10-30-80 and the addition of page la of 67 to the disposition instructions / justification dated 09-04-81 provide an adequate response to the close out of the design change request. This item is closed.
(Closed) Open Item (546/80-32-02; 547/80-32-02) Licensee to reevaluate IE Circular 78-16.
Upon reevaluation tne licensee determined that it indeed was applicable to the Marble Hill project. This item is closed.
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3.
Evaluation of Item Reported per the Requirerents of 10 CFR 50.55(e)
(Closed)10CFR50.35(e)ReportableItem(546/81-04-EE;547/8[-04-EE)
(Licensee designated number S81-09) Westinghouse had identified that a single random failure in the volume control tank level control system, in the absence of operator action, could lead to a loss of redundancy in the high head safety injection system for certain plant designs.
This item was reported by the licensee to Region III on May 27, 1981.
The licensee's final report on this item dated, June 24, 1981 was reviewed.
In additice, the following licensee corresjondence identi-fled by their document sequence number (DSN) were reviewed; 0528814000,
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0601815131, 0605814006, 0528814009, 0616813001 and 0624814000. This item is closed.
Incorporation of Westinghouse recommended actions, as defined in DSN 0601815131, into operating procedures prior to fuel load will be reviewed during a future inspection and is considered an open item.
(546/81-15-01; 547/81-15-01)
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Evaluation of Licensee Action with Regard to IE Bulletins and IL Circulars (Closed) IE Circular 78-16 (546/78-16-CC; 547/78-16-CC) Limitorque valve actuators. The following licensee correspondence identified by their document sequence number (DSN).were reviewed and found to be acceptable: 0801780051, 1130795010, 0917804000, 0911806518, 0916804018, 0923805075, 1002804007, 1009804001, 1024803000, 1024803001, 10248002, 1103804013, 1124804016, 0108814012, 1216803008, 0430813012, 0430813013, 0504815108, 0708815103, and 1208803001. This circular is closed.
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. 6 The incorporation of limitorque recommendations in their December 3,1980 letter _to PSI (DSN 1208805001), into operation and maintenance procedures will be reviewed during a future inspection and is considered an open item.
f,546/81-15-02; 547/81-15-02)
(Open).IE Bulletin 78-06 (546/78-06-BB; 547/78-06-B3) Defective Cuttler-Hammer type M relays with DC coils. The following licensee correspondance identified by their document sequence number (DSN)
were-reviewed; 0626780038 and 0705780108.
?he licensee's response stated "Each vendor of applicable-safety related electrical equipment utilizing DC control circuitry will be advised that Cuttler-Hammer type H relays with DC coils are unacceptable and will be requested to confirm (by letter) that such relays are not included in this equipment." This item. remains open pending the licensee demonstra-tion that the above actions have been taken.
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(Closed) IE Bulletin 78-10 (546/78-10-BB; 547/78-10-BB) Bergen-Patersor hydrau?ic shock suppressor accumulator spring coils. The following licensee correspondence identified by their document
sequence number (OSN) were reviewed and found to be acceptable:
0719780030 and 0724780012. This bulletin is closed.
(Closed) IE Bulletin 79-15 (546/79-15-BB; 547/79-15-BB) Deep draft pump deficiencies. The following licensee correspondence identified by their document sequence number (DSN) was reviewed and found to be acceptable: 0720794007, 0720794008, 0822790041, 0828790054, 0910790058.
This bulletin is closed.
(Closed) IE Bulletin 79-13, and IE Bulletin 79-13 revision 2 (546/79-13-BB; 547/79-13-BB; 546/79-13-1B; 547/79-13-1B) Cracking in feedwater system piping. The following licensee correspondence identified by their document sequence number (DSN) was reviewed, 0103805038. This Sargent & Lundy (S&L) document dated December 26, 1979 states that "Public Service cf Indiana will be required to submit a written response to the NRC pr!sr to obtaining an operating license." This is contrary to the fact that the original bulletin and revision 2 of the bulletin were sent to the licensee for informa-tion only and no written response is required to the NRC. NRC review of this bulletin is closed.
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5.
Exit Meeting
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.The inspector met with site staff representativer (denoted in the Persons Contacted paragraph) and the NRC Resident Inspector on
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September 3, 1981. The inspector summarized the scope and findings j
of the inspection.
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