ML20062C393
| ML20062C393 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/15/1990 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20062C391 | List: |
| References | |
| PEP-02.1, PEP-2.1, NUDOCS 9010310198 | |
| Download: ML20062C393 (5) | |
Text
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l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 INITIAL EMERGENCY ACTIONS PIANT EMERCENCY PROCEDURE:
PEP 02.1 VOLUME XIII Rev 028 Approved By:
MA Date:
!'hl790
'/
'Cener'al Manager /
Manager - Regulatory Compliance D
o 901031019e 903027 fDR ADOCK 05000324 PDC 1
E LIST OF EFFECTIVE PACES PEP 02.1 Page(s)
Revision 14 25 5
27 6
28 7 13 25 14 27 15 16 25 17 26 18 22 25 23 26 24 36 2,5 EAL 1 28 (10/15/90)
EAL 2 28 (10/15/90) h l
O BSEP/Vol. XIII/ PEP 02.1 i
Rev. 28
I Section 2 - Steam Line Break or Safetv/ Relief _ Valve Failure 2.1 Unusual Event 2.1.1 Reactor Coolant System pressure a 1250 psig.
E 2.1.2 Inability -a close an SRV with Reactor Coolaut System pressure
- s 900 psig.
CAUTION:
Failure is due to an overpressure event, not a test.
2.2 Alert Steam line break downstream of MSIVs or upstream of feedwater isolation valves as indicated by:
a.
Reactor trip with:
(1) Low RCS pressure (C32 R608 or C32 R60$)
E (2) Low steam pressure (C32 R609)
O
=
(3) Low reactor vessel water level (C32 R608)
E (4) liigh steam flow (C32 R603)
AED b.
Shift Operating Supervisor / Site Emergency Coordinator's opinion or evidence on P601 and P603 of continuing steam flow with steam line break outside of primary contain ent.
2.3 Site Emergency Alert indicated above and inability to isolate the leak.
E Loss of two out of three fission product barriers listed in Section 2.4 2.4 Ceneral Emergency Continued on next page.
BSEP/Vol. XIII/ PEP-02.1 6
Rev. 28
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