ML20063C313
| ML20063C313 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/26/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.02, TASK-2.K.3.17, TASK-TM NUDOCS 8205040677 | |
| Download: ML20063C313 (2) | |
Text
U b
p BALTIM ORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTlMORE, MARYLAND 21203 ARTHUR E. LUNDVALL. JR.
VICE PRES 6 DENT SUPP6v Sp,
M
, SQ~
. [.O P Office of Nuclear Reactor Regulation Q
S U. S. Nuclear Regulatory Commission Washington, D. C.
20555
/
co j
- 3
.v g Attn:
Mr. D. G. Eisenhut, Director d
C')
Division of Licensing 9h
.: G, Qi; !j
~
4
Subject:
Calvert Cliffs Nuclear Power Plant 7,
5
/
a s
Unit No. 1, Docket No. 50-317
&/
NUREG-0737 Item II.K.3.2 & II.K.3.17 N
m
/
References:
(a) Letter from D. G. Eisenhut to A. E. Lundvall, Jr.
dated 1/20/82.
(b) CEN-lh5, Final Report on PORV Reduction Methods dated December 1980.
(c) Letter from A. E. Lundvall, Jr. to D. G. Eisenhut dated 12/30/81.
(d) Letter from A. E. Lundvall, Jr. to R. A. Clark dated h/13/82.
Gentlemen:
In reference (a), you requested additional information on our PORV Reliability Analysis Report (submitted as reference (b)) and on emergency core cooling system (ECCS) outages (addressed in reference (c)).
Reference (d) was submitted to address concerns related to ECCS outages and the attachment to this letter is provided to answer some of the questions on PORV and safety valve analysis.
Additional information has been identified which should have been provided to you in reference (c), specifically, typical ECCS preventive maintenance outage duration data. The necessary data are being collected and will be provided by the end of May 1982. Remaining information related to safety and relief valves vill also be submitted as poon as it becomes available, in any case before the end of May.
,gf If you have any further questions on this subject, please do not hesitate to contact us.
/.
S Very truly yours, 8205040677 820426 PDR ADOCK 05000317 P
PDR KL l,,/(
. ww O2
\\
cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messrs. D. H. Jaffe - NRC R. E. Architzel - NRC
4' Attachment a
Mr. D. G. Eisenhut April 26, 1982 Additional Information Requested on NUREG-0737 Item II.K.3.2 Q.
Provide an explanation of the analysis yielding the probability of the failure of the operator to isolate the stuck-open PORV of 1.55 x 10-1 per demand.
A.
As stated in CEN-lh5, this value is based on data in Wash 1h00 Table III 6-1, " General Error Rate Estimates." The value used is the mean of the error rate at the operator's normal stress level and the error rate at se'rere stress levels.
The error rate at the operator's normal stress level was taken to be the sum of the estimated error rates where display is available in the control room and no arithmetic calculation is required. This result was rounded conservatively to 1.0 x 10-2, Severe stress level probability was taken as the upper value of the general error rate given very high stress levels where dangerous activitiesareoccurringrapidly,or3x10-1 The computed (mean) error rate was (3 x 10- + 1 x 162)/2 or 155 x 10-1 Q.
Show that the assumptions made and credits taken for plant reconfigurations and non-design improvements, in the CE generic report, are appropriate for Calvert Cliffs Units 1 and 2.
A.
As reported in our letter of February 20, 1981, all of the actione described in section F of CEN-lh5, " Implementation of Failure Reduction Program," have been implemented. The system at Calvert Cliffs is as described in the report.