ML13330A775
| ML13330A775 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/23/1979 |
| From: | Head J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7910090033 | |
| Download: ML13330A775 (4) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE J.
T.
HEAD, JR.
ROSEMEAD, CALIFORNIA 91770 TELEPHONE VIC-PRESIDENT 213-572-J472 May 23, 1979 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 202, Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94596 Attention:
R. H. Engelken, Director Docket No. 50-206 San Onofre Unit 1
References:
(1)
NRC (R. H. Engelken) letter to SCE (J. B. Moore) dated April 18, 1979, Docket Nb. 50-206 (2) SCE (J. T. Head, Jr.) letter to NRC (R.
H. Engelken) dated April 19, 1979, Docket lb. 50-206 (3) SCE (J.
H1.
Drake) letter to NRC (R. H. Engelken) dated May 3, 1979, Docket Nb. 50-206
Dear Sir:
The following information is in response to Item 13 of reference (1), which forwarded IE Bulletin 79-06A, Revision 1. In addition, the enclosed Table 1 provides the schedular information for completing the outstanding action items identified in our responses to items 1-12 which were submitted as part of references (2) and (3).
Item 13 Propose changes, as required, to those technical specifications which must be modified as a result of your implementing the above items [i.e., items 1-12 of IE Bulletin 79-06A and revision 1 thereto] and identify design changes necessary in order to effect long term resolution of these items.
(
(
-2
Response
One design change has been identified as necessary to effect long term resolu tion of the IE Bulletin items.
As discussed in our response to Item 3 of the IE Bulletin, per NRC direction, the low pressurizer level bistables have been placed in trip such that, when pressurizer pressure reaches the low setpoint, safety injection will be initiated irrespective of pressurizer level.
Our schedule for completion of the design change review is provided in enclosed Table 1.
No other design changes have currently been identified to effect long term resolution of IE Bulletin items 1-12.
However, our continuing review of the events associcate with the IIT incidenrt -my result i future design changes not directly associated with the bulletin items.
A complete review of the Technical Specifications against the actions taken in response to the IE Bulletin items was conducted.
One Technical Specification related to the operability of the pressurizer low level bistables has been identified.
However, it is our judgment that placing the bistables in trip does riot render them inoperable.
Therefore, we have concluded that the action taken does not violate the Technical Specifications and that no modifications are required at this tirie.
This matter was discussed with members of your staff.
Should you have any questions or require additional information, do not hesitate to contact me.
Sincerely, Enclosure cc:
Director, Office of Inspection and Enforcement, Division of Reactor Operations Inspection
TAILE 1 Outstanding Action Items Per IE Bulletin 79-06A Rev. 1 IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Peference Date
- 1. a) Review design basis accidents Item 1 August 15, 1979 and transients to identify conditions wherein pressurizer level may riot be indicative of reactor vessel level.
b) Revise operating instructions Item 1 September 15, 1979 as appropriate based on appraisal of above review.
- 2. Review emergency instructions to Item 1 June 15, 1979 insure that the actions to be taken by operators as specified in those instructions are consistent with revised Station Order S-0-104.
- 3. a) Determine potential for void Item 2 August 15, 1979 formation and methods for operator recognition and prevention.
b) Revise operating instructions Item 2 September 15, 1979 as appropriate based on appraisal of above review.
- 4.
Review design change implementing Item 3 August 15, 1979 NRC directive concerning pressurizer level/S.I.S. actuation in accordance with the Technical Specifications and 10CFPR 50.59
- 5.
When relief fram the requirement Item 5 Upon receipt of NRC for a standby operator is granted approval for deletion froma NRC, revise emergency operat-of the standby ing instructions to effect operator requiremnt.
timely manual initiation of auxiliary feedwater following transients and accidents.
- 6. Evaluate ability of POW isola-Item 6 June 30, 1979 tion valve to close with PORV wide open at design temperature and pressure.
IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Reference Date
- 7.
Review positioning requirements Item 8 July 31, 1979 and positive controls for engineered safeguard features valves and revise procedures as required.
- 8.
Review administrative controls IteM 10 July 31, 1979 for maintenance and testing of safety-related systems to ensure operabilit Ypnrtr to service.
Revise procedures as required.
- 9. Install an additional telephone Item 11 Completed on circuit to provide a continuous May 17, 1979 open cormmunication channel with NPC following prompt reportable occurrences.
- 10. Revise operating procedures Item 12 October 30, 1979 to provide appropriate action for hydrogen control.
PHiP:vppa