ML20214E266
| ML20214E266 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/26/1986 |
| From: | Buckman F CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8603070232 | |
| Download: ML20214E266 (4) | |
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flL Q James G Keppler, Administrator Region 111 US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
SUMMARY
OF CONFERENCE CALL The purpose of this letter is to document a conference call on February 26, 1986 between the Palisades Plant and Region III personnel regarding the outcome of maintenance efforts during the refueling outage to resolve the l
Safety Injection Tank (SIT) problem and to update the Region on current and future status.
t The topics discussed were as follows:
1.
Problems During the Last Run During the 1984-85 operating period CK-3116 developed a thru leak pressurizing the safety injection line which resulted in inleakage which diluted the SITS. This condition required repeated draining and filling of the SITS to return the boron concentration to acceptable limits.
It was noted that CK-3116 was the only loop check valve that leaked during that run; alno that it has been both the Palisaden Plant's and similarly designed plant's experience to have one or more loop check valves fail to seat initially, but do so during operation.
Leakage thru CV-2056 the three-way divert valve in the Chemical and Volume Control System (CVCS) was also discussed as an unrelated problem.
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J G Keppler, Administrator 2
Palisades Plant Summary of Conference Call February 26, 1986 2.
Maintenance Repairs During REFOUT a.
All four (4) SIT fill and drain valves were rebuilt, b.
All four (4) SIT pressure control valves were rebuilt.'
c.
Check valve, CK-3116, was rebuilt, d.
The CVCS three-way divert valve was replaced with a new valve of the same design.
Combustion Engineering engineers were brought onsite during the outage to provide consulting service for the repairs and resolution of the SIT inleakage problems.
In addition to the equipment repairs described, they recommended operation with CV-3069 open. This prevents pressurization of the common fill and drain header by draining to the Primary System Drain Tank; preventing backflow thru the fill and drain valves into the SITS.
3.
Present Plant Status The plant is presently pressurized in hot shutdown condition with the following equipment status:
a.
Loop 2B check valve, CK-3146, Icaks thru at 2.25 gpm with full system differential pressure (2000 psig) across it.
This is within allowable Technical Specifications leakage limits.
b.
The "D" SIT pressure control valve, CV-3038 is disabled in the closed position with the instrument air isolation from it.
Its manual isolation valve, MV-3038ES, is closed.
c.
The "C" SIT pressure control valve, CV-3047 is disabled in the closed position with the instrument air isolated f rom it.
Its manual isolation valve, MV-3047ES, is closed.
d.
CV-3069 is open to limit backpressure on SIT fill and drain valves, e.
The primary coolant system Icakage to the primary system drain tank is less than 0.4 gpm.
This leakage fa all thru closed CK-3146, closed MV-3038ES, closed CV-3038 and open CV-3069.
f.
Operation with the described line-up has been reviewed and found acceptable from an operability and safety standpoint by the Plant Review Conmittee.
g.
CV-2056 intermittently Icaks into the Clean k'aste Receiver Tanks.
This leakage is isolable with an accessibic manual valve.
l h.
The first stage of 4 stages in both Primary Coolant Pumps P-50A and l
P-50B are not " staged".
Each stage is designed to withstand full primary coolant system prennure.
OC0286-0035-NLO4
J G Keppler, Administrator 3
Palisades Plant Summary of Conference Call February 26, 1986 1.
Primary system leakage calculations are being performed daily with leakage thru CV-2056 isolated either by itself or by its isolation valve.
4.
Safety Aspects of Starting Up and Advantages for Doing So l
l Startup with the described equipment status was reviewed and considered i
acceptable for the following reasons:
l a.
Leakage thru the loop check valves is less than the allowable Technical Specification limits.
b.
Primary coolant system leakage is considerably less than both the allowable identified and unidentified Technical Specifications limits.
c.
Operation of the safety injection tank system is not compromised.
d.
Inleakage to the SIT's has been stopped by repair of the fill and drain valves and operation with CV-3059 open.
e.
Each of the four (4) stages in the primary coolant pump seals is designed to withstand full primary system pressure, I
f.
Leakage thru CV-2056 is isolable with an accessible manual valve.
g.
The disabled SIT prvasure control valves are in their fail safe position.
h.
Combustion Engineering engineers and the PJant Review Committee have reviewed the equipment status and concur ',ith startup.
i.
Technical Specification limits on PCS feakage are presently met and l
l provide adequate guidance for future operation if the leakage j
increases.
t 5.
Plans to Address Equipment Problems in the Future l
In the event the plant is shutdown to a cold shutdown condition, the following maintenance activities will take placer a.
The "C" and "D" SIT pressure control valves, CV-3047 and CV-3038, l
and "D" manual valve, MV-3038ES, will be rebuilt or replaced.
I b.
Loop 2B check valve, CK-3146, will be rebuilt.
c.
The CVCS three-way divert valve will be repaired or replaced.
d.
Both "A" and "B" Primary Coolant Pump Seals will be replaced.
i j
Consumers Power Company is cosmnitted to high standards of operation and maintenance at Palisades. We are not satisfied with a situation in which newly maintained equipment fails to meets its performance requirements, nor I
OC0286-0035-NLO4 1
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J G Keppler, Administrator 4
Palisades Plant Summary of Conference Call February 26, 1986 are we content returning the plan' to service with deficient equipment. Our choice, however, is one in which we either accept a substantial delay on return to power while we address the identified problems, or proceed with power escalation so that we may continue to identify equipment and system problems and assure that our first cold shutdown is one where we address the complete list of problema that exist.
Because the identified equipment deficiencies do not pese a problem to either compliance with our Technical Specifications or operation in a fashion that protects public health and safety, we view the more prudent course of action to be a continuation with plant operation.
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.,u f Frederick W Buckman Vice President Nuclear Operations i
CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident inspector - Palisades l
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OC0286-0035-NLO4
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