ML18045A545
| ML18045A545 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/04/1980 |
| From: | Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Bryan S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML18045A544 | List: |
| References | |
| TASK-15-02, TASK-15-2, TASK-RR AITS-F03085580, AITS-F3085580, NUDOCS 8008280345 | |
| Download: ML18045A545 (1) | |
Text
a uNtTEo sTATEs I
NUCLEAR REGULATORY COMMISS N
REGION Ill 799 ROOSEVELT ROAD GLEN ELLYN. ILLINOIS 60137 August 4, 1980*
MEMORANDUM FOR:
S. E. Bryan, Assistant Director for Field Coordination, Division of Reactor Operations Inspection, IE "THRIJ:
A4 / R.
- Heishman, Chief,. Reactor Operations and Nuclear (J/' /
Support Branch *
.FROM:
stmJECT:
J. F. Streeter, Chief. Nuclear Support Section 1 REQUEST TO CHANGE PALISADES TECHNICAL SPECIFICATIONS (AITS F03085580)
This memorandum is forwarded for action.
There are two problems associated with the ability of Palisades to cope with a steam line rupture accident; One problem is that only one high pressure safety injection (HPSI) pump and one charging pump would be operable following a steam line rupture assuming a loss of offsite power and the failure of an emergency diesel generator.
This single-failure problem las been previously brought. to the attention of.IE:HQ (see AITS F30379H2) and NRR and is being reviewed as part of _the Sys.tematic Evaluation Program.
Tl:ds is a troublesome matter since a recen-t report by the staff* "Loss of Off site Power-Survey Status Report", appears to indicate **that the Palisades site has been parti-culaz:ly susceptible to loss of offsite power occurences.
(There may be other single failures not related to loss of off site po¥er which could prevent the plant from coping with the accident.
We assume the SEP will cover these possibilities as well as the loss of offsite power).
The second problem, *to our knowledge, has not been previously identified to IE:HQ or NRR and is the reason for writing this memorandum.
The analysis of the Steam ~ine Rupture Incident for Palisades was conducted based upon the assumption that two of -the three HPSI pumps and two of the three charging pumps are available.
Technical Specifications 3.3.2.c and 3.2.3.a>r~spec-: -*
tively, allow power operations to continue for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with only one BPSI pump and one.charging pump operable.
Therefore, the plant is all<JWed to operate for a relative;Ly long (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> plus an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> before having to be in hot shutdown) period of time in a situation..,here the plant could not meet the accident analysis flow assumptions even if one does not assume a single failure.
We request that you promptly forward thi.s matter to NRR with a request. for NRR to arrange to have the technical specifications changed.
cc:
D. Boyd P. Wohld 80 B. Jorgensen o 8 2 B*f13YS-
~~
J. F. Streeter, Chief Nuclear Support Section 1