ML19329C213
| ML19329C213 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/07/1976 |
| From: | Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Roy G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19329C211 | List: |
| References | |
| NUDOCS 8002120934 | |
| Download: ML19329C213 (4) | |
Text
.
.ia..
UNITED STATES NUCLEAR REGULATORY COMMISSION nEGloN lli 799 ROOSCVELT RO AD GLEN CLLYN, ILLINOIS 60137 May 7, 1976 C. W. Roy, Chief, FicId Coordination and Enforcement Branch Office of Inspection and Enforcement,lleadquarters STATUS OF PREPARATION OF DAVIS-BESSE I (TOLEDO EDISON COMPANY, DOCKET NO. 50-346) FOR OPERATION As of the present date, the Reactor Operations and Nuclear Support Branch evaluates the status of the Davis-Besse I facility to be as follows as regards preparation for operation:
Licensee Fuel Load Date September 28, 1976.
(We understand this date is under review by licensee; no formal announcement made as of this date.)
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 i
does not increase.
Construction Status j
The Construction Branch indicates that construction of the facility is i
essentially complete. The major outstanding issues related to construction j
of this facility include:
1.
Electrical Construction Quality Assessment - Approximately 1400 elements for consideration.
Reinspection of this area tentatively scheduled for early June 1976.
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 of containment vessel.
- 6. - Questions regarding containment paiat quality are in process of resolution. This issue expected to be resolved by early June 1976.
8002ISS [.3f
-r...
m r.m
.m.,--,.,
,_,,y,
C. W. Roy May 7, 1976 7.
Quality assessment of safety related snubbers and hangers (piping and components) remains to be accomplished.
Preoperational Testing As of the end of April 1976, there are approximately 168 preoperational tests identified for completion prior to loading fuel. Approximately 65% of the associated test procedures are approved with more than 90%
in some stage of development. Of these 168 identified tests:
1.
Nine tests are completed and approved.
2.
Three tests are completed and under review.
3.
Twenty-eight tests are partially completed.
Procedure Development We estimate the status of approved procedures as follows:
Operating - 80%
j Emergency - 80%
Maintenance - 70%
Surveillance - 20% (Substantial reduction from previous report because reported fraction was based on previous version of Technical Specifications.
Substantial revision required due to adoption of Standard Technical Specifications format.)
Administrative - 60%
The licensee is aware that procedure development is to be completed by 90 days prior to fuel loading (by July 1, 1976).
Radiological and Emergency Preparedness The Fuel Facility and Materials Safety Branch indicates that there are no unresolved items identified at the present time that would pose a possible delay to fuel loading at the unit as a result of their inspection activities.
Inspection of the environmental monitoring programs of the licensee was conducted in April 1976.
Inspection of Emergency Plan preparedness of the licensee is scheduled for mid May 1976.
Training All formal training committed to 1.2 the FSAR is essentially complete.
Training activities are currently directed towards preparation for license examinations which are currently scheduled for August 1976.
v r..,.
C. W. Roy May 7, 1976 Physical Security and Material Accountability No fuel has yet been received on site (presently scheduled to begin July 6, 1976). The Security Plan is being reviewed by Reactor Licensing and accountability procedures are under development.
No inspections have been conducted in this functional area.
Operations Quality Assurance Preparedness This functional area was inspected during April 26-29, 1976.
A substantial number of major programmatic and implementation problems were identified.
The nature and extent of these problems are such that substantial reinspection activity will be required.
Full implementation by the licensee of an adequate Quality Assurance Program for Station Operation as described in Section 17.2 of the FSAR by 90 days prior to their scheduled fuel load date appears improbable at this point. Our inspection activities will be adjusted to follow the licensee's program development and
-- i implementation progress in these areas.
Unresolved Matters The major unresolved matters at this point, relative to station operation, include:
1.
Satisfactory completion of the licensee's Test Program commitments.
2.
Satisfactory development and implementation of their Quality Assurance Program for Station Operation.
The current status of the facility with regard to preoperational testing and quality assurance program development 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. An ACRS subcommittee site visit is scheduled }by 18, 1976 to review the status of the plant, with the subcommittee scheduled for July 1976 and the full committee scheduled for August 1976.
If you have any questions on these matters, please do not hesitate to contact me.-
f
?A$b0 C. Fiorelli, Chief Reactor Operations and Nuclear Support Branch cc: See next page P
L.
s G. W. Roy my 7, M76 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 i
i