ML18052A634
| ML18052A634 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 08/05/1986 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Buckman F CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8608070195 | |
| Download: ML18052A634 (2) | |
See also: IR 05000255/1986014
Text
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Docket No. 50-255
Consumers Power Company
ATTN:
Dr. F. W. Buckman
Vice President
Nuclear Operations
212 West Michigan Avenue
Jackson, MI
49201
Gentlemen:
AUS o 5 1986
This refers to your response dated July 17, 1986 to the violation identified
in IE Inspection Report 86014.
In your response you stat~d that ANSI N 18.7
does not require that each test assure that the acceptance limits contained in
applicable design documents are satisfied. Further you indicated that the
current operational surveillance program, in conjunction with the testing
performed during the preoperational phase and subsequent to maintenance,
modification and procedural changes, address as an overall test program, the
requirements of ANSI N 18.7-1976.
The requirements of the ASME B&PV Code,
Section XI, and the Palisades Technical Specifications are used as a basis for
monitoring pump degradation.
We agree that the elements you outlined are necessary for a testing and
surveillance program which meet the requirements of ANSI 18.7-1976, the B&PV
Code,Section XI and the Palisades Technical Specifications. However, with
respect to Section XI requirements associated with surveillance testing of the
Auxiliary Feedwater System (AFW), your program was not adequate to assure the
AFW system will perform as described in the FSAR.
Specifically, the
parameters contained in your surveillance test (i.e., DP, NPSH, vibration,
discharge pressure, etc.) could have degraded to the point where the minimum
flow required from each AFW pump during accidents requiring AFW flow would not
be met.
These same degraded parameters measured against the Section XI
requirements would be within the band of acceptable pump operation.
Our
concern relative to this problem was the basis for our violation.
Further review of other safety related system surveillance tests by the
Resident Inspectors identified the absence of verification of recorded
parameters with design document flow requirements.
While we recognize that
the Section XI pump performance parameters may be adequate to assure
acceptable performance of safety related pumps, your program as currently
implemented did not provide assurance that the minimum flow requirements
stated in design documents would be met.
Based on this review, you were
requested to determine if the problem identified with the Section XI
surveillance testing might apply generically to other safety system surveillance
tests.
Your response addressed the generic question and refers to enhancements to the
surveillance testing program to positively demonstrate that each of the
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auxiliary feedwater pumps meets the FSAR Accident Analysis flow requirements.
This course of action appears adequate and no further response to this letter
is required.
Should you wish to further discuss this matter, please feel free to contact
Mr. B. L. Burgess of my staff.
cc:
Mr. Kenneth W. Berry, Director
Nuclear Licensing
J. F. Firlit, General Manager
DCS/ RSB (RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII
Ronald Callen, Michigan
Public Service Commission
Nuclear Facilities and
Environmental Monitoring
Section
RII\\~
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18/04/86
RIII
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I ould~mond
Sincerely,
Charles E. Norelius, Director
Division of Reactor Projects
RIII
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