IR 05000440/1985034

Insp Repts 50-440/85-34 & 50-441/85-16 on 850530-0726.No Violations Noted.Major Areas Inspected:Instrumentation Cables & Terminations,Drywell Integrity Test & Plant Tours

ML20134E251
Person / Time
Site:	Perry
Issue date:	08/15/1985
From:	Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20134E232	List: IR 05000440/1985034 ML20134E229
References
50-440-85-34, 50-441-85-16, NUDOCS 8508200106
Download: ML20134E251 (4)

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I U. S. NUCLEAR REGULATORY COMMISSION

REGION III

f Reports No. 50-440/85034; 50-441/85016 Docket Nos. 50-440; 50-441 Licenses No. CPPR-148; CPPR-149 Licensee: Cleveland Electric Illuminating Company Post Office Box 5000 i Cleveland, Ohio 44101 Facility Name Perry Nuclear Power Plants, Units 1 and 2 Inspection At: Perry Site, Perry, Ohio Inspection Conducted: May 30 through July 26, 1985 t

Inspector: D. E. Keating Approved By: R. C n d'

Reactor Projects Section 1C Date k

Inspection Summary Inspection on H.1y 30 through July 26. 1985 (Reports No. 50-440/85034(DRP):

No. 50-441/85016(DRP))

Areas Inspected: Review of documentation concerning 10 CFR 50.55(e), inspec-tion and documentation review of instrumentation cables and terminations, witnessing of drywell structural integrity test, review of procedures for program covering extended construction delay, and plant tours. The inspection covered 136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> onsite by the resident inspector including 35 off-shift hour Results: No violations were identified. No significant safety issues were identified during this inspection perio ,

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DETAILS Prepared By: D. E. Keating Reviewed By: R. C. Knop Persons Contacted Cleveland Electric Illuminating Company

• C. M. Shuster, Manager, Nuclear Quality Assurance Department

• E. Riley, Supervisor, Quality Assurance, Construction Quality Section

• K. Cimorelli, Lead Quality Engineer, Electrical Unit, Construction Quality Section E. Parker, Unit Supervisor, Piping, Instrumentation, and Controls, Construction Quality Section E. C. Christiansen, Senior Engineer, Nuclear Construction Engineering Section Weiss, Janney, and Elstner G. Hedien, Senior Engineer D. Heidbrink, Engineer Gilbert Associates, In C. Angstadt, Senior Structural Engineer The inspector also contacted and interviewed other licensee and contractor personnel during this inspection perio * Denotes those attending one or more of the exit meeting . Licensee Action on 10 CFR 50.55(e) Items (92703)

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l (Closed) 10 CFR 50.55(e) - (440/84043-EE)(DAR 207): Potential Deficiency l of Fuel Control Levers on Transamerican Delaval Standby Diesel Generator The inspector reviewed the letter from Transamerica Delaval notifying the NRC and the licensee of a 10 CFR Part 21 concerning the identification of certain Standby Diesel engines supplied to a number of construction sites without 1/4" diameter retaining pins. The lack of these pins plus the loss of proper cap screw tension could lead to engine unavailability. The inspector also reviewed the licensee's notification to the Region of the I

potential 10 CFR 50.55(e) concerning this ite _ _ _ _ _ . _ _ _ _ _ _ _ - _ _

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The licensee conducted a thorough inspection of this concern and deter-mined that the cap screws associated with the control shaft levers and injection pump levers were torqued to the manufacturer's recommendations and that all retaining pins were in place as require In order to assure the availability of these engines through surveillance of this condition, the licensee wrote a nonconformance (0QS-1173) and dispositioned it to track the adjustment and torquing of cap screws oa the control shaft levers and injection pump levers, and to assure that all pins are in place. Based on the inspection referred to above and these additional actions, the licensee had withdrawn the potential 10 CFR 50.55(e).

This item is, therefore, considered close . Instrument Cable and Terminations (52063B)

The inspector physically inspected pulled stainless steel jacketed cables for circuits 1-D19-RIA, 4A, 11B, and 14B for Divisions I and II. Also reviewed was the documentation concerning this activity. As indicated, cabling for four (4) circuits had been pulled and terminated. Cabling for eight (8) more circuits needs to be installed. These cables have not yet arrived onsite. The inspector will be notified when they do arrive in order to witness receipt inspection activities prior to witnessing pulling and terminatio The documentation for the four (4) pulled circuits appeared to be in order. Nonconformances (NRs), Field Variance Authorizations (FVAs), and Engineering Change Notices (ECNs) clearly stated the conditions to be addressed and adequately dispositioned. The necessary signatures were present and the dates of signatures were in proper sequence. These activities will continue to be monitored during future inspection . Status of Nuclear Grade Coatings (92706)

During a walkdown of the Drywell in conjunction with the Structural Integrity Test, the inspector observed two (2) SRV downcomers that had exposed areas of metal. Upon closer observation there were two (2) areas, one (1) above, the other below, the lugs of a two (2) unit snubber support and several areas along the fillet welds of the snubber support lugs where the coatings had either rubbed off or buckled due to pipe movemen This condition was brought to the licensee's attentio The licensee was already aware of this and several other areas where this condition exist NRs have been written and dispositioned to change the coating. Test samples of the new coating have been made and site exposure tests are nearly complete. The samples of the new coating have been made and site exposure tests are nearly complete. The samples will then be sent to Oakridge, Tennessee for nuclear evaluation and qualification. This item will continue to be monitored during future inspections. This is con-sidered an open item (440/85034-01(DRP).

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.- Drywell Structural Integrity Test (63700)

A regional based inspector and the resident inspector accompanied licensee personnel on several walkdowns as they attempted to perform the Drywell Structural Integrity Test. Problems were encountered with a boot-type flexible connection on the SRV piping and their associated penetrations through the Drywell wall into the suppression pool. The problems con-cerned the rupturing of the boot material during pressurization. NRs were written covering a total of 13 of these boots. After three (3)

previous attempts resulting in boot failures, the test was suspended

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during the fourth attempt at 4:01 a.m. on July 27, 1985 after attaining 18.7 psig. The test will be performed at a later date in conjunction with or during a window in the Loss of Offsite Power Verification Test.

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I The inspectors also reviewed the accumulated structural data. This will be addressed in more detail in Regional Inspection Report 50-440/8504 . Review of Quality Assurance For Extended Construction Delay (92050)

The inspector has reviewed Procedure PNPP 5541 and PPD Interface Document 7-0301. These documents present the maintenance program that controls the activities pertaining to periodic inspection of Unit 2 equipmen A walkdown of equipment and areas is planned in the near future in order to establish a reference point for the prescribed periodic inspections required in I.P. 9205 . Plant Tours and Housekeeping (92706)

The inspector made numerous tours of the Control Complex, Containment, and Drywell, noting the conditions in these areas after temporary demobilization for the pending series of tests and the nature of work remaining to be completed. Overall housekeeping has improved greatly and is being maintained on a continuous basi It is expected that this level of activity will continu . Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or both. An Open Item is identified in Paragraph 4 of this repor . Exit Interviews (30703)

The inspector met singularly and in conjunction with a region based inspector, the persons noted in Paragraph 1 on July 2 and August 1, 1985 to discuss the scope and results of the inspections. The licensee did not identify any proprietary concerns relating to the inspectio l l

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