IR 05000206/1983012
| ML20023C477 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/03/1983 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20023C476 | List: |
| References | |
| TASK-2.B.1, TASK-2.B.2, TASK-2.K.3.25, TASK-TM 50-206-83-12, NUDOCS 8305170365 | |
| Download: ML20023C477 (4) | |
Text
,.
-
.
.
.,
.
U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-206/83-12 Docket No. 50-206 License No. DPR-13 Lice.see:
Southern California Edison (SCE) Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Unit 1 Inspection at:
Sar, Onofre Site, San Clemente, California Inspection conducted-April 5-29, 1983 Inspectors:
_2 h
3/,hM
.
D. F! KTrsch, Chief Dat6 Signed Reactor Projects Section No. 3 Rea tor Projects Branch No. 2 d
g
.$
&
V Approved by:
D. F. Kirsch, Chief
~' /~~
'
Reactor Projects Section No. 3 Reactor Projects Branch No. 2 Summary:
Inspection on April 25-29, 1983 (Report No. 50-206/83-12)
Areas Inspected: Routine announced inspection of the licensee's implementation of TMI ::ct ion item commitments and requirements. The inspection involved 18 inspactor hours by one regional based supervisor.
Results: No items of noncompliance or deviations were identified.
8305170365 030503 PDR ADOCK 05000206 G
-
.
.
.,
O DETAILS 1.
Individuals Contacted
- H. B. Ray, Station Manager
- J. M. Curran, Manager, Quality Assurance
- W. C. Moody, Deputy Station Manager
- P. A. Croy, Manager, Configuration Control and Compliance
- M. A. Wharton, Station Engineer
- J. M. Francis, Compliance Engineer
- M. Speer, Compliance Engineer
- G. W. Mcdonald, QA/QC Supervisor
- R. N. Schweinberg, Construction Manager
- J. J. Wambold, Maintenance Manager H. A. Timmons, QA Engineer
- T. Broughton, Construction Field Engineer R. Kreiger, Licensing Engineer, Supervisor L. Bennett, Licensing Engineer J. Schramm, Shift Supervisor
- Denotes principal attendees at the April 29, 1983 Exit Meeting.
In addition, the SONGS-1 NRC Senior Resident Inspector was in attendance at the exit meeting.
2.
TMI Action Items (
a.
(Closed) Item II.B.1 - Reactor Coolant Vent System The inspector performed the following procedure and document examinations relative to this item:
Proposed Facility Change 80-36
.
Work Package 3.2
.
Startup to Station Turnover Package
.
l System Flush Records
.
System Hydrostatic Test Records
.
Preoperational Test Procedure TI-TMI-3.2.3 and data records
.
Sample of circuit cable pull, termination and test records l
.
Construction Inspection Data Reports for pipe spools
'
.
Sample of Field Welding Checklists and Filler Metal Withdrawal
.
Sheets Sample of Pipe Support / Anchor Bolt Inspection Records
.
Operating Instruction S01-4-1, Rev. 4 - Filling and Venting
.
the Reactor Coolant System Operating Instructicn S01-4-2, Rev. 2 - Draining the Reactor
.
Coolant System Operating Instruction S01-4-33, Rev. 0 - Post Accident Reactor l
.
Coolant Vent System Operation Operating Instruction S01-4-42, Rev. 0 - Reactor Coolant
.
System Alignment
t
--
.
.,
d Engineering Procedure S01-V-2.15, Rev. 4 - Inservice Testing
.
Program, ASME Class 1,2 and 3 Valves Piping and Instrumentation Diagram Drawing No. 568776, Rev.
.
17 with Change Notice No. 24 Valve Logics Train A Drawing No. 235859
.
Valve Logics Train B Drawing No. 235858
.
Reactor Coolant Vent System Isometric Drawing No. 5180750-1
.
Letter from K. P. Baskin (SCE)'to D. M. Crutchfield (NnR)
.
dated April 1, 1982 Submitting Design Details for the Reactor Coolant System Vents Letter from K. P. Baskin (SCE) to D. M. Crutchfield (NRR)
.
dated June 1, 1982 Responding to an NRR Request for Additional Information In addition, the inspector performed field examinations of the installed valves and selected piping, pipe supports, electrical conduit, electrical junction box supports, pipe support welds, piping welds and pipe support U-Bolt installations. The above activities were examined for compliance with selected commitments contained in licensee submittals, identified above, and installation detail drawings and procedures.
The above examination. efforts were conducted to establish whether:
emergency procedures have been developed which reflect the use
.
of the reactor coolant system vents procedures define the conditions under which the vents should
.
and should not be used
.
operating personnel have been trained in the use of reactor coolant system vent procedures the requalification training program provides training in the
.
use of reactor coolant vent procedures the reactor vessel head and reactor coolant system vent
.
modifications are in accordance with commitments the design changes were reviewed and approved in accordance
.
with Technical Specifications and established QA/QC controls the design changes were controlled by established procedures
,
.
test results were reviewed and evaluated and within previously
.
established acceptance criteria operating procedure modifications were made and approved in
.
acccrdance with Technical Specifications as-built drawings were changed to reflect the modifications
.
i
!
.- - - -.. -
-
- -
.--
- - - -. - -.
,
- - - _. _ _. - -..
-
- *
.-
.
The licensee has submitted the procedure for Post Accident Reactor Coolant Vent System Operation (No. S01-4-33, Rev. 0) to NRR for review and approval as required. The licensee stated that the Reactor Coolant Vent System valves will be added to the Inservice Test Program, as Category B, when the NRC permits operability testing.
No items of noncompliance or deviations were identified.
b.
(Closed) Item II.B.2 - Plant Shielding On November 9,1982 Region V representatives conducted an inspection of modifications required by the shielding design review. The modifications were verified to be completed and in agreement with the listing and diagram supplied by the licensee.
Subsequent to this inspection, the NRC issued a Safety Evaluation for this item, attached as an enclosure to a letter from D. M.
Crutchfield (NRR) to R. Dietch (SCE), dated April 18, 1983.
Based upon the above, this item is closed.
No items of noncompliance or deviations were identified.
c.
(Closed) Item II.K.3.25 - Loss of AC Power on Reactor Coolant Pump Seals By letter dated January 11, 1982, the licensee informed NRR that calculations indicated that the reactor coolant pump seals can withstand a complete loss of AC power, both onsite and offsite, for at least two hours because of the seal cooling provided by the DC pump.
NRR evaluated that information and determined that the licensee adequately demonstrated that the integrity of reactor coolant pump seals was maintained during a loss of offsite power event and was acceptable. By letter, dated July 7, 1982, from D. M. Crutchfield (NRR) to R. Dietch (SCE) this item was considered to be resolved for SONGS-1.
No items of noncompliance or deviations were identified.
3.
Exit Meeting The inspector met with licensee representatives, denoted in paragraph 1, at the conclusion of the inspection on April 29, 1983 and discussed the inspection scope and findings.
.