ML19319C375

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Discusses Status of Preparation of Facility for Operation. Facility Not Expected to Load Fuel in 1976 If Present Rate of Sys Turnover for Operation & Associated Rate of Sys Testing Does Not Increase
ML19319C375
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/23/1976
From: Fiorelli G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Roy G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML19319C373 List:
References
NUDOCS 8002140759
Download: ML19319C375 (3)


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UNITED STATES NUCLEAR REGULATORY COMMISSION RECloN 111 799 ROOSEVELT RO AD GLEN ELLYN, lLLINOIS 60147 March 23, 1976 G. W. Roy, Chief, Field Coordination and Enforcement Branch Office of Inspection and Enforcement, Headquarters STATUS OF PREPARATION OF DAVIS-BESSE I (TOLEDO EDISON COMPANY, DOCKET NO. 50-346) FOR OPERATION As of the pres' t daen, the Reactor Operations and Nuclear Support Branch evaluatt

    • tt of the Davis-Besse I facility to be as fcilows as regar-

.an for operation:

Licensee Fuel Loau --.e September 28, 1976 As noted in our February 18, 1976 memorandum, we would not expect this unit to load fuel in 1976, if the present rate of system turnover for operation by the licensee and the associated rate of system testing does not increase.

Construction Status The Construction Branch indicates that construction of the facility is essentially complete. The major outstanding issues related to construction of this facility include:

1.

Electrical Construction Quality Assessment - Approximately 1400 elements for consideration.

2.

Instrumentation Quality Assessment (construction aspects).

3.

Safety related and balance of plant valves not installed as yet (approximately 600 units).

4.

Primary system hydrostatic testing.

5.

Construction proof testing oi containment vessel.

6.

Questions Jegarding containment paint quality are in process of resolution; 7.

Quality assessment of safety related snubbers and hangers (piping and components) remains to be accomplished.

8002140f[f

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G. W. Roy March 23, 1976

,Preoperational Testing As of the end of February 1976, there are approximately 168 preoperational tects identifieC for complecion prior to loading fuel. Approximately i

50% of the associated test procedures are approved with more than 90%

in some stage of development. Of these 168 identified tests:

1.

Six tests are completed and approved.

2.

Six tests are completed and under review.

3.

Seventeen tests are partially completed.

Procedure Development We estimate the status of approved procedures as follows:

Operating - 80%

Emergency - 80%

Maintenance - 70%

Surveillance - 60%

Administrative - 80%

The licensee is aware that procedure development is to be completea by 90 days prior to fuel loading (by July 1,1975).

Radiological and Emergency Preparedncas The Fuel Facility and Materials Safety Branch indicates that there are no unresolved items identified at the present cime that would pose a possible delay to fuel loading at the unit as a result of their inspection activities.

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Training 1

All formal training committed to in the FSAR is essentially complete.

Training activities are currently directed towards preparation for license examinations which are currently scheduled for August 1976.

Physical Security and Material Accountability No fuel has yet been received on site (scheduled to begin July 6,1976).

The Securi:y Plan is being reviewed by Reactor Licensing and accounta-bility procedures are under development. No inspections have been conducted in this functional area.

.o.

a ao G. W. Roy March 23,.1976 Operations Quality Assurance Preparedness This functional area f s scheduled for inspection 1.uring the latter part.of April 1976.in accordan e with MC 2513.

Unresolved Matters Satisfactory completion of the licensee's Test Program Commitments remains the major operational unresolved item.

The current status of the facility with regard to preoperational testing makes it impractical to provide you with other than a general status report as above. As the pace of preoperational testing accelerates, we will continue to update this report in greater detail to keep you fully informed of the licensee's progress. The ACRS subcommittee will be at the site on April 20, 1976, to review the status of the plant, with the full committee scheduled for May 6, 1976.

If you have any questions on these matters, please do not hesitate to contact me, fA G. Fiorelli, Chief Reactor Operations and Nuclear Support Branch cc:

D. Thompson, IE:HQ B. H. Grier, IE:HQ K. V. Seyfrit, IE:HQ R. F. Warnick, Regional Coordinator J. G. Keppler, Regional Director

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