ML19329B726

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Forwards Region 3 Summary of Status of Const,Preoperational Testing,Ie Insp Program & Outstanding Items.Licensee 770209- 16 Fuel Loading Date Believed Optmistic
ML19329B726
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/01/1976
From: Thompson D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Boyd R
Office of Nuclear Reactor Regulation
References
NUDOCS 8002060735
Download: ML19329B726 (7)


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Roger S. Boyd, Director Division of Project Panagement STATUS OF PRZPA2ATIO:i FOR OPER.CID:i 0F DAVIS-BESSZ U' IT '!o. 1 TOLEDO ZDISIC3 COMPANY DOC.CT :40. 50-346 Concerning Davis Eesse Unit !!o 1, our *tegion III Office has prepared a four part sumary which is enclosed, describing IE's assessment of the status of construction, the status of preoperational testing, the status of the II inspection program, and outstanding items including enforc.1-ment and unresolved items.

As indicated in Cnclosure 3, the licensee now estimates the:y vill be ready to load fuel February 9 - 16, 1977. IE believes this date is optimistic,

'>ut capable of bein ; achieved if no substantive problems developed during testing activitica.

Orftiel i3 seed as f

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Dudley '!hompson, Acting Director Division of Field Ouerations Office of Inspection and Enforcement

Enclosures:

As stated cc:

w/ enclosures R. C. DeYoung, ER J. F. Stolz,:in2

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CONSTRUCTION STATUS Systems for Which Construction is Not Completed, Over 85% of the subsystems have been released to operations. The remaining 43 1

subsystems have yet to be completed and re;. eases are not expected to result in delaying facilit.y startup.

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I Construction Punch List On two occasions, the yoke failed on the reactor coolant pump seal injection isolation valve, MU-HV66B.

The cause of the failures has not been identified.

Also, although not considered contributing to the failures, investigation of this matter revealed that the yoke material for this valve and six other valves from the same supplier did not meet seismic requirements. Further review is planned to establish that yoke material for valves supplied by other ccmpanies meets requirements.

Facility startup could be delayed by adverse findings in the investigation of the above identified item. No problems are anticipated in the examination and resolution of other construction punch list items.

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ENCLOSURE B PREOPERATIONAL TESTING STATUS

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The licensee now estimates fuel loading ~will begin on February 9-16, 1977.

Based on the test program schedule and the progress of testing, we believe this date to be optiaistic, but capable of being achieved if no substantial system problems develop during the testing activities.

At the present time, the licensee has identified a total of 199 preoperational and startup tests in their testing program.

Of these, approximately 174 are scheduled for completion prior to fuel loading.

These 174 preoperational tests are categorized as follows at the present time (as of November 1, 1976):

Test Cateeorv No. of Tests Partially Comoleted Comoleted Comoleted & Aceroved I

54 14 5

3 II 28 10 4

1 III 13 4

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IV 79 21 11 9

174 49 21 13 Thus, out of 174 preoperational tests, 34 are now completed, 49 are in progress and 91 have yet to be initir.ted.

A1'1 startup test procedures are either completed or in an advanced stage of

. development.

As noted in Enclosure A, completion of these procedures are expected by 60 days prior to fuel loading.

Two safety related systen deficiencies have developed thus far in the testing program:

1.

The licensee is having to modify the lubrication system for the high pressure injection pump bearings due to temperature proble=s.

Resolution of this problem is expected by late November 1976.

Submittal of detailed infor=ation on these changes for NRR review is planned for January 1977.

2.

Operation of the diesel generator units results in high te=peratures on the control panels, including protective relays of the diesels.

This results from the generator cooling air being discharged directly against the panels.

The licensee is presently evaluating alternatire correction methods.

Neither of these two items are currently on the critical path for the testing program; however, resolution of the pump bearing problem is necessary by late November to prevent schedule slippages.

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i ENCLOSURE C e

STATUS OF RE0_UIRED INSPECTION Construction Inspections All routine construction inspection requirements have been completed. Some follow-up inspections for electrical cabling remain pending development of design and acceptance criteria by the licensee, and review and acceptance by NRR.

Preoperational Testing and Operat1onal Preparedness Inspections 1.

Operations All Reactor Operations inspections are being completed in accordance with the inspection schedule with the following exceptions:

a.

QA Program Operations:

Several program deficiencies were iden-tified and are being resolved. This inspection requirement should be completed by 60 days prior to fuel loading, except for the Surveillance Testing Program. Due to late Technical Specification revisions, this program had to be revised, and inspection of this area will be completed by 30 days prior to fuel loading.

b.

Preoperational Test Procedure Reviews: This inspection activity is incomplete due to the licensee finalizing test procedures.

More than 90% of the 200 identified preoperational and power as-cension test procedures have been completed, reviewed and approved. This inspection activity should be completed by 60 days prior to fuel loading.

a 2.

Emergency Planning Inspection requirements remaining prior to 0.L.:

a.

Offsite Agencies b.

Facilities, Equipment, Procedures

'c.

Test and Drills No current outs:anding items. These inspection requirements scheduled for aid November 1976.

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Enclosure C.

3.

Environmental Protection Inspection requirement remaining prior to 0.L.:

Environmental Protection - Final Preoperational Inspection No current outstanding.tems: The inspeedon is scheduled for aid December.

4.

Radioactive Waste Systems Inspection requirements remaining prior to 0.L. :

a.

QC and Capability Test Partially completed. Will be completed when all of the required counting equipment is operational. Agreement with the Commission's reference laboratory will be a requirement prior to IE recoc=ending the issuance of an 0.L.

Remainder of inspection tentatively scheduled for mid December 1976.

b.

Liquid, Solid and Gaseous Radwaste Systems These inspection requirements are approximately 50% complete.

Completion of the above inspections are awaiting completion of system testing and training activities of the licensee. The following is the estimated schedule for these systems:

Clean Liquid Radwaste System - turned over to licensee; testing to be completed after HFT.

Miscellaneous Liquid Waste System - turnover December 1976; testing January 1977.

Gaseous Radwaste System - Turnover January 1977; testing February 1977.

Solid Radwaste System - Turnover November 1976, testing as personnel available.

5.

Radiation Protection Radiation Protection inspection requirements are approximately 50%

complete. Completion of these requirements are dependent upon the completion dates of system testing (e.g., area radiation monitors, etc.) and personnel training. Reinspection of this area is ten-tatively scheduled for January 1977.

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Enclosure C.

6.

Physical Protection Reinspection of security items noted during the inspection on August 4-6, 1976, will be conducted in early January.

Telephonic notification is being provided by the licensee on the status of the identified items on at least a monthly basis.

Region III has suggested to ONRR that a representative of that office be onsite during the reinspection.

Startup Testing Inspections No conditions presently exist which would prevent completion of required inspections on schedule.

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ENCLOSURE D GJTSTANDING ITES INCLUDING ENFORCEMENT AND UNRESOLVED ITEMS Uncorr'ected Items of Noncomoliance At the present time, all the uncorrected items of noncompliance are capable of resolution prior to issuance of the 0.L. with the possible exception of the following:

The present installation of sensing lines for reactor containment vessel particulate monitor precludes obtaining a representative sample.

(IE Inspection Report No. 050-346/76-13.)

(Further' review of this matter is scheduled for the next inspection.

It appears further revisions for this monitor as well as other particulate monitor installations may be required to meet requirements of ANSI N13.1-1969.)

Unresolved Items No problems resulting in facility startup delays are anticipated in the resolution of unresolved matters identified as of November 10, 1976.

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