ML20092B096
| ML20092B096 | |
| Person / Time | |
|---|---|
| Site: | Fermi |
| Issue date: | 06/13/1984 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| EF2-68193, NUDOCS 8406200055 | |
| Download: ML20092B096 (3) | |
Text
W:yne H. J:n3 Vc3 Persnient Nuclear Operations Detroit Edison EEf?'
June 13, IP 4 EF 2-6 819.'
Director of Nuclear Reactor Regulation Attention:
Mr. B.
J.
Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Youngblood:
Reference:
(1)
Fermi 2 (2)
Letter from Detroit Edison to NRC, EF2-53421, dated May 29, 1981 (3)
Safety Evaluation Report for Fermi 2 (SER), NUREG-0798, July 1981
Subject:
Reporting Failures of Safety / Relief Valves Fermi 2 FSAR, Sec tion II. II.K. 3. 3, presently requires the following:
" Detroit Edison will report a failure of a safety / relief 7
valve to open or close when called upon within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by phone; the report will be confirmed by telegraph (or similar transmission) the first working day following the event and followed up with a written report in 2 weeks.
This written report will be in the form of a Licensee Event Report This position is consistent with both Reference 2 and Section II.K.3 of Reference 3.
Ilowever, as you are aware 10CFR50.73 was recently added to the regulations.
Consequently, the above referenced FSAR section will be revised in a forthcoming amendment and the applicable implementing documents (e.g., Technical Speci-fications, plant procedures) have been or will be revised to reflect a 30-day schedule for submittal of the subject report.
This report will be in the form of a Licensee Event Report.
In addition, the reporting requireuents of the newly amended 10CPR50.72 will apply if the situation warrants.
0406200055 840613 PDR ADOCK 05000341 A
{
Mr.
B.
J.
Youngblood June 13, 1984 EF2-68193 Page 2 The attachment provides the proposed FSAR revision.
If you have any questions, please contact Mr. Keener Earle at (313) 586-4211.
1 Sincerely,
/
/
5-
)
/
cc:
Mr.
P.
M. Byron
- Mr.
M.
D.
Lynch
- USNRC, Document Control Desk
- Washington, D.C.
20555 6
- With attachment
EF-2-FSAR H.II.K.3.3 Report Safety and Relief Valve Failures Promptly and Challenges Annually H.II.K.3.3.1
' Statement of Concern l
l The record of relief valve failures to close for all BWRs in the past 3 l
years of plant operation is approximately 30 in 73 reactor years (0.41 l
failures per reactor year). This has demonstrated that the failure of a relief valve to close would be the most likely cause of a small-break LOCA.
The high failure rate is the result of high relief valve challenge rate and a relatively high failure rate per challenge (0.16 failures per challenge).
Typically, five valves are challenged in each event. This results in an equivalent failure rate per challenge of 0.03.
H.II.K.3.3.2 NRC Position All future safety and relief valve challenges and failures should be reported to the NRC.
This should include the prompt reporting of failures through Unusual Event Reprots and the reporting of challenges in the annual report (Reference 1).
H.II.K.3.3.3 Detroit Edison Position Detroit Edison will report a failure of a safety / relief valve in accordance with 10CFR50.73 and guidance presented in NUREG-1022. This written report will be in the form of a Licensee Event Report in accordance with plant reporting requirements.
If appropriate and applicable, reporting will also be done in accordance with 10CFR50.72.
The Detroit Edison annual report to the NRC will list each safety / relief valve that is challenged during the year and will include the number of times each valve is challenged.
l l
H.II.K.3.3.4 Reference j
1.
U.S. Nuclear Regulatory Commission, Generic Evaluation of Feedwater Transients and Small-Break Loss-of-Coolant Accidents in CE-Designed j
Operating Plants and Near-Term Operating License Applications, NUREG-0626, pp. 1-16, item B.14, January 1980.