ML18057A836
| ML18057A836 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/03/1991 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML18057A837 | List: |
| References | |
| NUDOCS 9104090094 | |
| Download: ML18057A836 (3) | |
See also: IR 05000255/1990020
Text
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Pi.PR .. a 1s:n
Docket No.
50-255
Consumer~ Power company
ATTN: -David P. Hoffman
.Vice President
.. Nuclear Operations
1945 West Parnell Road
Jackson, Michigan 49201
Gentlemen:
SUBJECT:
NRC INSPECTION REPORT 50~255/90020(DRS)
This refers to the special safety inspection conducted by
Ms~ v. P. Lougheed and Mr. J. D. Monninger of t.his office on
September 4, * 1990, through March 28~ 1991, of activities at the
Palisades Nuclear Plant~ authorized by NRC Operating License
No. DPR-20, and to the discussion of our findings with
Mr. K. M. Haas, and others of your sta.ff,. at the conclusion
of the inspection.
The enclosed copy of our inspection report identifies areas
examined during the inspection.
The purpose of this inspection
was to review allegations concerning the potential for a post
loss of coolant accident return to criticality due to
insufficient ~afety injection tank boron concentration and for
a hydrogen burn due to additional sources of aluminum inside the
Within these areas, the inspection
consisted of selective examinations of prdced~res and
representative records, observations, and interviews with
personnel.
Additionally, a detailed review of material submitted
by your staff, the alleger, and available test data in regard to
these allegations was performed by the Off ice of Nuclear Reactor
- Regulation.
The results of this inspection determined that both of the
concerns identified were of some merit.
Regarding the first
issue, the NRC determined that a return to criticality could not
be ruled out based on realistic assumptions; however, this return
would not significantly impact the. course of post LOCA recovery
from a safety standpoint.
Regarding the second issue, the NRC
determined that the maximum hydrogen concentration values present
in the FSAR were incorrectly low; however, the correct value
would still be below flammability limits.
910.4090094 910403
ADOCK 05000255
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Consumers Power Company
2
APR - 3 139~
While no violations of NRC requirements are contained in the:
enclosed inspection report,* the Unresolved Items identified
in the inspection' report are being reviewed* for'* potential
- enforcement ~ctions. -You will be notified by subsequent
correspondence of-our decision regarding enforcement actions
associated. with the issues covered by this inspection .. No
written response is required at this time.
-
In accordance with 10 CFR 2~790 of the Commission's regulations,
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NRC Public Document Room.
We will gladly discuss any questions you have concerning this.
inspection.
Sincerely,
,...,- ir.tt* 1 i' ~IGNED B.Y. _T_ .. 0.. M,.'\\RTlt{
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. T. o. Martin, Director
Division of Reactor Safety
Enclosures:
1.
Inspection Report
No. 50-255/90020 (DRS)
2.
Safety Evaluation on the
Potential for a Return to
Criticality Following a
Large Break LOCA at Palisades
3.
Safety Evaluation Regarding
the Post"'."'LOCAHydrogen Analysis
4.
Safety Evaluatiori Supporting
Technical Specification
Amendment No. 136
See Attached Distribution
R&V~tr
Lougheed/cg
03/~'/91
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~rniet ~Jorgensen Pawl~
03/Z7/91
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03/~~/91
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Martin
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.Consumers Power Company
Distribution
Gerald B. Slade, General Manager
D. J.*vandeWalle, Safety and
Licensing Director:
.DCD/DCB (RIDS)
OC/LFDCB
Resident Inspector, RIII
Jame's R. Padgett,* ,Michigan Publi"c * .
. Servic*e CoJ!l.missicn
Michigan Department of
Public Health
Palisades, LPM, NRR
.
3
. B. Holian, NRR/Licensing Project Manager
D. Funk, Allegations Coordinator (3 copies)
APR * 3 .1991