IR 05000440/1985079
| ML20137W293 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/06/1985 |
| From: | Guldemond W, Hare S, Maura F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20137W273 | List: |
| References | |
| 50-440-85-79, NUDOCS 8512100218 | |
| Download: ML20137W293 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-440/85079(DRS)
Docket No. 50-440 License No. CPPR-148 Licensee: ' Cleveland Electric Illuminating Company Post Office Box 5000 Cleveland, OH 44101 Facility Name:
Perry Nuclear Power Plant, Unit 1 Inspection At:
Perry Site, Perry, OH Inspection Conducted:
November 4 through ovember 22, 1985 Inspectors:
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Date
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swa Approved By:
W. G.
ulde nd, Chief
/e -6-Y Operational Programs Section Date Inspection Summary Inspection on November 4 through November 22, 1985 (Report No. 50-440/85079(DRS))
Areas Inspected:
Routine, announced inspection by two region based inspectors of Safety Evaluation Report issues; previous inspection findings; local leak rate test (LLRT) procedures; LLRT performance witnessing; LLRT results review; and post-integrated leak rate test work on the containment liner.
The inspection involved 34 inspector-hours onsite by one NRC inspector including four inspector-hours during off-shifts.
An additional 17 inspector-hours were expended by two NRC inspectors in the Region III office.
Results: Of the six areas inspected, no violations or deviations were fidentified.
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DETAILS 1.
Persons Contacted Cleveland Electric Illuminatin Company,(~CEI)
~@. M. Shuster, ManageF,~Te~rFy,g i; clear QuaTity Assurance Department a.
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- M. D. Lyster, Manager, Perry Plant Operations Department
- J. J. Waldren, Manager, Perry Plant Technical Department
- F. R.' Stead, Manager, Perry Nuclear Engineering Department
- S. Kensicki, Superintendent, Perry Plant Technical Department
- W. Kanda, General Supervisory Technical Engineer
- G. H. Gerber, Elerent Administration Supervisor
- E. M. Root, Element Mechanical Supervisor
- J.J. Lansby, Supervisor, Quality Engineering
- E. " Bu11elli, Senior Licensing Engineer
- B.
I Stetson, Operations Engineer
- J. L. Hansen, Surveillance Coordinator
- T. Hethesly, Compliance Engineer
- D. R. Hoffman, Operations Engineer
- B. B. Liddel, Operations Engineer
- N. J. Lehman, Operations Engineer
- G. Charles, Surveillance Engineer
- B. S. Ferrel, Licensing Engineer
- D. Thompson, System Engineer
- V. J. Concel, ISI Coordinator B. Cooper, System Engineer b.
US NRC
- J. A. Grobe, Senior Resident Inspector, Operations
- S. Stasek, Resident Inspector, Dresden The inspector also contacted other personnel during this report period.
- Denotes personnel present at the exit interview on November 21, 1985.
2.
Safety Evaluation Rep _ ort Fol_lowup Perry Safety Evaluation Report (SER), Revision 2, Section 6.2.6, entitled Containment Leakage Testing, requires the High Pressure Core Spray, Low Pressure Core Spray LPCS, and the Low Pressure Coolant Injection pump discharge lines to the reactor vessel be Type C tested with air and the largest leakage included in the 0.60 La limit for penetration and isolation valve leakage. This item was tracked as Confirmatory Issue 24 (SER 1.10)
and Open Item (440/85022-40(DRS)). Following a review of the licensee's local leak rate test program and their close out package, this item is considered closed.
No violations or deviations were identified.
3.,
Previous Inspection Findings a.
(Closed) Open Item (440/85031-01(DRS)): The licensee has determined that existing administrative controls coupled with the tack welding
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-of.the plugs to the lockout nuts are adequate to prevent the removal of penetration guard pipe alignment plugs which could create a containment leak path. -This evaluation is acceptable.
b.
(Closed) Open Item (440/85031-02(DRS)):
The licensee has obtained relief from NRR to water test their feedwater check valves.
Following this relief, the licensee successfully leak tested the feedwater check valves with water as the test medium.
The inspector determined the leak rate associated with these valves had a negligible effect on the integrated leak rate test results.
4.
Local Leak Rate Test Procedure Review The inspector reviewed procedure SP IE61-001, Revision 0, entitled Local Leak Rate Special Test, for technical adequacy and conformance with the requirements of 10 CFR 50, Appendix J, Technical Specifications, FSAR Commitments, and the Safety Evaluation Report.
The main body of the
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procedure implements the performance of local leak rate tests through Surveillance Instructions for the individual penetrations. A review of the main body of the procedure revealed several discrepancies which, when discussed with the licensee's staff, were addressed by temporary changes to the procedure.
The inspector reviewed 50 percent of the Surveillance Instructions which implemented the performance of local leak rate test requirements for contaminant isolation valves. While modified significantly by the use of' temporary procedure changes, the procedures appeared to be technically sound and satisfy requirements and commitments.
No violations or deviations were identified.
5.
Local Leak Rate Test Witnessing-No LLRT's were preformed during th's inspection period.
The performance of LLRT's has been completed at the Perry plant for the preoperational phase.
The licensee informed the inspector that LLRT's will be performed early next year as a result of maintenance activities by operations personnel.
The inspector requested in the exit interview that the licensee notify him approximately two days prior to performing LLRT's on systems previously identified by the inspector.
The licensee acknowledged the inspector's request.
No violations or deviations were identified.
6.
Local Leak Rate Test Results Review The inspector reviewed the following completed Surveillance Instructions to determine if the licensee was following the procedures and if the results recorded were acceptable:
Surveillance Instruction System SVI M17-T9208 Containment Vacuum Relief
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Surveillance _ Instruction System
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SVI M14-T9313 Containment Purge Supply SVI N27-T9414 Reactor Feedwater
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SVI B21-T9416 Main Steam I
SVI E51-T9422 Steam Supply to RCIC P
SVI B21-T9423 Main Steam Line Drain SVI E12-T9431 Residual Heat Removal The review revealed no significant probicms with the completed test packages. Additionally, the inspector noted that all temporary procedure l
changes made were in accordance with plant policy and a concerted effort was made by the test group to perform the tests correctly.
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Several of these packages were reviewed on November 22, 1985, the day after the inspector's exit interview with the understanding that if any i
problems were identified, the inspector would notify the licensee. No problems were identified during this post exit interview review.
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No violations or deviations were identified.
7.
Review of Work on Containment Liner
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In previous discussions with the licensee the inspectors stated that after the performance of the Structural Integrity Test (SIT) and Integrated Leak Rate Test (ILRT), work on the containment liner should be controlled in
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such a manner as to not invalidate the SIT /ILRT results. To make this determination, the inspector performed a containment liner walkdown to ascertain whether or not work had been performed on the liner since the performance of the SIT /ILRT. The inspector found one* example of minor work that had been performed on the liner and noted'this to the licensee L
requesting tFat they supply documentation showing how this work had been
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controlled.
In addition, the inspector requested the licensee identify any additional work that had been performed on the liner.
As a result of the first request the' licensee provided appropriate documentation to the inspector. As a result of the second request, the i
licensee identified two additional items, all three items being listed
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l-belcw:
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Description
- Removal of several temporary attachments from the containment liner - NR-CQC-4194 l-Repair of a sleeve to insert weld on penetration V-313 - NR-CQC-4064
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Installation of permanent cap plates for spare penetrations E-302 and P-303 The licensee supplied an integrated package covering all the above liner work to the inspector.
After reviewing this package the inspector determined this work had been performed in a controlled manner and concluded that the work had no deleterious effect on the structural strength or leak tightness of the containment structure.
No violations or deviations were identified.
8.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
for an exit interview on November 21, and summarized the scope and findings of the inspection activities to date.
The inspector noted to the licensee that he had not completed his inspection in the area of completed LLRT package review (paragraph 6) and that inspection activities would continue through November 22, and if any problems were identified, he would notify the licensee.
No problems were identified after the exit interview.
The licensee acknowledged the inspector's statements.
The inspector discussed the likely informational content of the inspection report with regard to documents reviewed by the inspector during the inspection.
The licensee did not identify any such documents as proprietary.
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