ML18045A778
| ML18045A778 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/13/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010150311 | |
| Download: ML18045A778 (4) | |
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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0650 October 13, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5.
U S Nuclear Regulatory Commission Washin~on, D C 20555 DOCKET 50-255 -
LICENSE DPR PALISADES PLANT - FIRE PROTECTION MODIFICATIONS -
REQUEST FOR CHANGE TO REQUIRED IMPLEMENTATION DATE On September l; 1978, Amendment 42 to the Pali.sades Plant*license was issued to levy specific requirements pertaining to Fire Protection.
Table 3.1 of the attached SER prescribed twenty-three modifications to be implemented in order to upgrade the plant's ability to safely sustain and respond to a major fire, and specified a required implementation date for each modification.
To date,
. twenty bf the twenty-three items have been implemented; a. request has been made to defer one item (3.1.11 Independent Shutdown Path); and two items are due to be implemented in October, 1980 (3.1. 6 Rerouting of Power and Control Circuits; 3.1.15 Reactor Coolant Pi.lmp Oil Collection Sy$tem).
By letter dated September 28, 1979, we requested that the SER be modified to defer the implementation date for item 3.1.11, Independent Shutdown Path.
This request is being treated as a separate.item and will not be addressed in this letter..The remai.ning SER i terns, 3.1. 6 and 3.1.15 represent only a small part of the Fire Protection Program as a whole.
Completion of these items will repre-sent only a small additional increment in the level of fire safety over that 1which
.has already been achieved.
- A. description of the action remaining on each of' these
.items is.as follows:
- 3.. 1.6 Rerouting of Power.and Control Circuits*
- --As....:the-p:lant-was--or.iginJ!.ilY_ designed, both 125 VDC buses and the distribution panels for operating and control-power. ro-some-equ:i-pment-.imp.or.tant_ to safe* shut-down were located in the cable spreading room (See Figure l).
The init:fal-intent*--c ____ _
as reflected in the SER was to reroute selected cables to provide physical separa-tion.
As our design progressed, it was decided that an alternate approach would be followed which is clearly superior to rerouting of cables.
This alternate approach provides two new DC distribution panels supplied directly from the batteri-es and located such that they are independent of the cable spreading room (See Figure 2).
Since the new.panels could not be procured in time to allow installa-l _
tion during previous plant.shutdowns this modification remains incomplete.
An out-f§'"'I' age.of approximately two weeks duratio~ will be required to complete this modifi-t\\,04:.. \\
cation.
.~ /
\\
8 0 10 l 5 1 03 I I
r)
- Mr Dennis M Crutchfield, Chief Palisades Plant October 13, 1980 3.1.15 Reactor Coolant Pump Oil Collection System 2
By letter dated May 2, 1980, installation of the oil collection system was report-ed to be complete.
Subsequent review, however~ revealed that some potential leak sources still existed which are not adequately covered by the installed systems.
These potential sources include the upper and lower motor bearing drain and fill plugs, sight glasses and the lower bearing oil reservoirs.
As we discussed in our letter of September 9, 1980, additional drip pans and drain lines will be installed.
An outage of approximately three - five days duration will be requir-ed to complete this modification.
In view of the relatively small amount. of work remaining, and the substantial improvements in the level of fire safety which have already been achieved, we do not feel that a plant outage specifically to complete these modifications is warranted.
It is therefore requested that the implementation dates for modifica-tions 3;1.6 and 3.1.15 be changed to require implementation by either the first forced outage of sufficient. expected duration which would allow this work to be done, or the 1981 refueling outage presently scheduled for October, 1981.
David P Hoffman Nuclear Licensing Administrator CC Director, Region III, USNRC NRC Resident Inspector - Palisades Attachment - Figures 1 & 2
125V D-C SYSTEM PORTIONS OF PRES~NT DESIGN 010 125V o-:c BUS NO. I 020 125V 0-C BUS N0.2 OPERATING & CONTROL POWER FOR:
D*G NO 1-1 2400V BUS 1-C 480V BUS 13 NO. I BATTERY. ROOM I
I I
i I I B~TTERY NO. I 2400V SWGR 1-C ROOM i
I I I I I
Oii 125V D-C DI ST. PNL NO. I CABLE
'SPREADING ROOM 021 125V 0-C DIST. PNL N0.2 OPERATING & CONTROL POWER FOR:
0-G NO 1-2 2400V BUS 1-0 IIBOV BUS 14 N0.2 BATTERY ROOM BATTERY N0.2 DIESEL GEN 1-2 ROOM FIGURE I
- .J
I I
I I
I 125V D-C SYSTEM MODIFICATIONS TO PRESENT DESIGN DIO 125V D-C BUS NO.I
. DI I 125V D~c DIST. PNL NO. I CABLE SPREADING ROQM D20 125V D-C BUS N0.2 D21 125V D-C DI ST. PNL NO. 2 NO.I BATTERY ROOM NON-AUTO
->sHUNT TRIP<....-
2ij0QV SWGR 1-C ROOM I
BATT~RY NO. I I
i i
. I i
OPERATING & CONTROL.
POWER i FOR:.
D-G 11.1 2ij00V/ BUS 1-C ij80V BUSS ES 13 & I ij AUX s/.D. PANEL (C150) i I
I i
I I
DllA 125V D-C DIST. PNL NO. IA BATTERY N0.2 OPERATING & CONTROL POWER FOR:
D-G 1-2 2ij00V BUS 1-D D21A 125V D-C DI ST. PNL N0.2A
- THESE ~USES INSTALLED ONLY DURING. PERIODS OF MAINTENANCE WHEN BATTERY OPEN-CIRCUITED I
I N0.2 BATTERY ROOM DIESEL GEN 1-2 ROOM
. FIGURE 2