ML20197G397
| ML20197G397 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/02/1984 |
| From: | Houston R Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20197F919 | List: |
| References | |
| FOIA-86-489 GL-83-28, NUDOCS 8405170235 | |
| Download: ML20197G397 (2) | |
Text
'
[p @ *'%g t
UNITED STATES 1
NUCLEAR REGULATORY COMMISSION I
- (
WASHINGTON, D. C. 20555
["
"/
g
[
\\,
MAY 2 1984 MEMORANDUM FOR-i" N I~ -
I C,.....~..--&
R. Wayne Houston, Assistant Director for Reactor Safety FROM:
Division of Systems Integration DIABLO CANYON 1&2 - REVIEW 0F DESIGN FOR AUTOMATIC SHUNT TR
SUBJECT:
FOR SCRAM BREAKERS Plant Name: Diablo Canyon Units 1 and 2 Docket No.:
50-275 & 50-323 Licensing Status: 0L TAC No.: 53171 Responsible Branch:
LB #3 Project Manager:
H. Schierling Review Branch:
ICSB Review Status: Complete By letter dated December 20, 1983, pacific Gas and Electric Company (PG&E) provided a response to Generic Letter 83-28 including Item 4.3, Reactor Trip System Reliability (Automatic Actuation of the Shunt Trip Attachment for W plants). Included was a response to pant specific questions identi-fied in the NRC evaluation of the Generic Westinghouse design which was submitted by the Westinghouse Owner's Group on June 14, 1983.
Enclosed is our safety evaluation report (SER) which addresses the licen-see's response to Item 4.3 of Generic Letter 83-28. We find the design modifications acceptable conditioned on:
a) Submission of test procedure used to independently verify operabil-ity of the undervoltage and shunt trip cevice, b) Confirmation of the seismic qualifications of shunt trip attacinents and the associated circuitry.
c) Submission of results of life cycle testing and conclusions related to response time testing.
d) Submission of revised test procedure for manual reactor trip testing.
e) Submission of the proposed technical specification changes to require periodic testing of the undervoltage and shunt trip functions.
Contact:
N. Trehan, ICSB X27589
[
m 7%5 l}6R39"
l T. Novak ICSB considers their actions on this TAC complete since the enclosed SER sets forth conditions which will permit an acceptable design.
Enclosed is the SALP input for this review.
I
,k { f.
e %-
~~
R.' Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration
Enclosures:
As stated cc:
R. Mattson G. Knighton H. Schierling e
4
ENCLOSURE D
ICSB SALP INPUT PLANT:
Diablo Canvon - Units 1 & 2 MW
SUBJECT:
Review o'f Desian for Automatic Shunt Trip for Scram Breakers
} %ld EVALUATION PERFORf1ANC' BASIS CRITERIA CATEGORY 1.
Manacement.
Involvemen]
N/A No basis for assessment.
2.
Approach to 1
An understandina of the issue was demonstrated.
Resolution of Technical Issues 3.
Responsiveness 1
Technically sound and thorough responses to NRC initiatives were made to effect a timely resolution.
4.
Enforcement N/A No basis for assessment.
History The reporting of the desian modifications for automatic shunt 5.
Reportable Events 1
6.
Staffing N/A No basis for assessment.
7.
Training N/A No basis for assessment.
pJ ucog
' ],,
UNITED STATES t
8' NUCLEAR REGULATORY COMMISSION o
7.
p WASHINGTON. D. C. 20555 N*****/
JUL 10 1984 MEMORANDUM FOR:
tJ t ^ M W + 0irector for Licensing, Division of Licensing FROM:
R. Wayne Houston, Assistant Director for Reactor Safety, Division of Systems Integration
SUBJECT:
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 -
SER SUPPLEMENT NO. 24
References:
(1) Petition filed by Government Accountability Project Institute For Policy Studies on February 2, 1984 (2) Letter from D. A. Brand to H. R. Denton, dated March 29, 1984 (3) Letter from B. W. Sheron to G. W. Knighton, dated April 19, 1984 (4) Letter from G. W. Knighton to J. O. Schuyler, dated May 21, 1984 (5) Letter form J. O. Schuyler to G. W. Knighton, dated May 24, 1984 (6) Letter from J. O. Schuyler to G. W. Knighton, dated June 6, 1984 (7) Lettcr from J. O. Schuyler to G. W. Knighton, dated July 2, 1984 Plant Name:
Diablo Canyon, Units 1 and 2 Docket Number:
50-275/323 Licensing Stage:
OL Responsible Branch:
Licensing Branch #3 Project Manager:
H. Schierling DSI Review Branch:
Reactor Systems Branch Review Status:
Awaiting Information to this memo provides Reactor Systems Branch inputs to Diablo Canyon Units 1 and 2 SSER No. 24.
These inputs include the staff evaluatiun of the petition filed by Government Accountability Project Institute for Policy Studies (GAP) on February 2, 1984 (Items No. G, 153, 154, 155, 159, 162, 167, and 169) and the updated information on the allegation Hos. 39 and 45.
Our evaluations reflect information in the reference letters.
Contact:
C. Liang, x24754
.t -
M9?'lh7'
-Thomas M. Novak JEM-10 1984 Please note that the part of GAP 169 with regard to the administrative actions of PG&E is outside the RSB review scope and is not included in Enclosure 1. contains the staff SALP evaluation.
p.p IW....
'l,.< ? l ).
t
! w'
'r R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration
Enclosure:
As stated cc:
D. Muller RSB S/Ls R. Capra H. Schierling F. Rosa A. Marchese G. Knighton i
s.
e
C. LC f(ofW
% /ww
/
/
ENCLOSURE 2 SALP INPUT The purpose of this enclosure is to document our evaluation of the licensee's performance during DSI's Safety Evaluation R_eview.
The following criteria from NRC Appendix 0516 are the only ones relevant to this evaluation.
1.
Management Involvement in Assuring Quality This action was handled by personnel at the appropriate level of management.
The utility involved the necessary in-house technical staff.
Rating.
Category 2 2.
Approach to Resolution of Technical Issues The applicant performed the work required.
The quality of applicant's submittal, was satisfactory.
Rating:
Category 2 3.
Response to NRC Initiatives The applicant's responses to the NRC's Request for Additional Information-(RAI) was satisfactory.
Rating:
Category 2 4.
Overall Rating:
Category 2 a
h l
l
,