ML19209A915
| ML19209A915 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/31/1979 |
| From: | Head J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7910050620 | |
| Download: ML19209A915 (6) | |
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Southern California Edison Company gE
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August 31, 1979
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U. S. fluclear Regulatory Commission L
j Office of Inspection and Enforcement StJd10n v Suite 202, Walnut Creek Plaza 1990 North Callfornia lloulevard Walnut Creek, California 94596 Attention:
Mr. R. II. Engelken Director Docket flo. 50-206 San _Onofre Unit 1
References:
(1)
SCE (J.T. llead, Jr.) to rl!<C (it.II. Engelken) dated April. 19, 1979, Docket. 50-206 (2) SCE (J.ll. Drake) letter to flRC
( R.ll. En o,elken) dated May 3, 1979, Docket flo. 50-206 (3) SCE (J.T. Ilead, Jr.) letter to llRC (it.l!. Engelken) dated May 23, 1979, Docket flo. 50-206 (4) SCE (J. T. Ilead, Jr.) let.ter to flRC l
j 777 (R. II. Engelken) dated June 25, 1979,
.r JJI Docket 50-206 (5) flRC (D. L. Ziemann) let.ter to SCE (J.11. Drake) dated August 7, 1979, Docket 50-206 Refe r <ac es (1), (2) and (3) provided our responses to IE Bulletin 79-06A and Revision 1 thereto which rertuested information concerning the Three
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Hi1e Island Incident..
lieferences (1) and (2) addressed IE Bulletin Items 1-12 while Reference (3) addressed IE Bulletin Item 13 and provided schedular infortnation for completing t.he outstanding action items ident.ified in References (1) and (2).
Reference (4) provided additional information to supplement our responses submitted by hererences (1), (2) and (3).
p 7910050 f*88
PDCR BRl8l Ma s The purpose of this let,ter is to provide updated schedular infortnation for outstanding action items ident,1fied in References (1), (2) and
( 14 ).
The original schedular informat, ion was provided by references (3) and
( 14 ).
To facilitate your review, the updat,ed schedules have been consolidated from the above references and are cross referenced to the IE Bullet,in action items in the enclosed Table 1.
Out, standing iteras il and 7 require plant specific input from our reactor supplier (Westinghouse) prior to completion. Schedules for these items have been extendeb to reflect the most recent Westinghouse proposals.
West,inghouse has indicated that the abnormal workload related to Three Mile Island and the large amount of plant specific work which must be accomplished for Sen Onofre Unit 1 have bben the o mmi rmn t factors in the extended schedules.
Out, standing items la and 3a also require input from Westinghouse,
flowever, this input is predominantly generic in nature and has therefore been incorporated int,o the Work Scope of the Westinghouse TMI owners Group.
Schedules for these items have not yet been formalized, but will be made available to you when they are developed.
Tr.e procedure changes we are making to complete our action on Out, standing Items 9 and 10 are in the final review stages.
A summary of these changes will be submi t ted as rmjues ted by Refe rence (5).
Should you have any questions or require additional information, do not, hesitate to contact me.
Sincerely.
R'
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Enclosure cc:
Director, Office of Inspection and Enforcement Division of Reactor Operations Inspection
!!04 338
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. bec:
J.E. Thomas (SDG&E)
R.L. Erickson (SDO&E)
D.R. Pigott (Chickering & Gregory) 0.J. Ortega/J.H. Drake A. A. Arenal J.T. Ilead, Jr.
R.S. Currie H.L. Ottoson J.M. Curran E.L. Curtis R.R. Erunet J.R. Tate C.R. Kocher/J.A. Eeoletto K.P. Paakin D.E. INan J.G. Haynes U.C. fiood y G.T. !!cLandrich R.U. Krieger/P.H. Penseyres J.L. Rainsberry
!!RC Files ED1 Files J. Signorelli (flus) 9
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TABLE 1 Outstanding Action Items Per IE Eulletin 79-06A Rev. 1 IE Bulletin 79-05A Scheduled, completion Item Description Rev. 1 heference Date 1.
a)
Review design basis accidents Iten 1 Incorporated into and transients to identify Westinghouse Till conditions wherein pressurizer Owners Group.
l,'o level may not be indicative of schedule at this time.
reactor vessel level.
b)
Revise operating instructions Iten 1 One month after as appropriate leased on appraisal completion of la above of above review.
2.
Review emergency instructions to Item 1 Comple ted insure that the actions to be taken by operators as specified in those instructions are consistent with Station Order S-0-104.
3 a)
Determine potential for void Item 2 Incorporated into formation and methods for Uestinghouse T!!I operator recognition and Owners Group.
!!o prevention.
schedule at this time, b)
Revise operating instructions Item 2 One month after based on appraisal of above completion of la above review to:
(i) assure that action steps specifically warn of potential for voiding with a description of all instrumentation which night provide indication of potential or actual voiding, (ii) specifically address operator actions, based on operational modes and instrument indication discussed above, for terminating conditions tending to lead to void formation and (iii) provide operators with guidance for enhancing core cooling given the unexpected conditions of actual voiding in primary system.
1104 340
-S-IE f;ulletin 79-06 A Scheduled Completion Item Description Rev. 1 Reference Date c)
Provide a sur. mary of the results of Item 2 Two weeks after the review (Iten 3a) and subsequent completion of the procedure revisions (Item 3b).
review.
d)
Provide station operators with Item 2 Completed interim information regarding instrumentation available to detect core voiding and verify natural circulation.
4 4.uv n:w design chanbe implementing NRC Item 3 October 31, 1979 directive cor.cerr.ing pressurizer level /S.I.S. actuation in accordance with the Technical Specificaticus and 10CFR 50.59.
5.
Revise operating procedures to require Item 4 Completed manual actuation of all automatic containment isolation valves in the event of automatic initiation of safety injection.
6.
When relief fron the requirement Iten 5 Upon receipt of NHC for a standby operator is granted fron approval for NHC, revise emergency operating deletion of the instructions to effect tinely manual standby operator initiation of auxiliary feedwater requirement.
following transients and accidents.
7.
Evaluate ability of PORV isolation Item 6 October 31 1979 valve to close with PORV wide open at design temperature and pressure.
8.
Review emergency operating Item 7 Completed instructions to identify and resolve any conflicts with the safety injection termination criteria.
9 a)
Review positioning requirements Item 8 August 28, 1979 and positive controls for engineered safeguard features valves and revise procedures as
- required, b)
Provide a summary of the results Item 8 August 28, 1979 of the review and any procedural revisions to NRC.
1104 341
?00R ORIGIEL IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Reference _
Date
- 10. a)
Eeview administrative controls Item 10 August 28, 1979 for maintenance and testing of safety-related systems to verify operability of redundant safety-related systems prior to removal frcn service and to ensure operability upon return to service. Revise procedures as required.
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Au;ust 23, 1979 of the review and any procedurel revisions (Item 10(a)) to NRC.
- 11. Install an additional telephone Item 11 Completed circuit to provide a continuous open communication channel with tiRC f ollowing prompt reportable occurrences.
- 12. Revise operating procedures Iten 12 Completed to provide appropriate action for hydrogen control.
I'l!P :mpp i104 342