ML20084S450
| ML20084S450 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/16/1971 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084S447 | List: |
| References | |
| NUDOCS 8306170012 | |
| Download: ML20084S450 (5) | |
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) Power
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/ [) e oenerai omces: aim we. wemo.n Avenue, sackson, ucNgen 4o2oi . Area code ei7 7ss.osso September 16, 1971 Dr. Peter A. Morris, Director Re: Docket No 50-255 Division of Reactor Licensing License No DPR-20 US Atomic Energy Commission Washington, DC 205+5 1
Dear Dr. Morris:
This letter is written to apprise you of a recent incident involving the primary coolant system at this facility.
At the time the incident occurred, the plant was in a hot shutdown condition with the primary coolant system at refueling boron concentration, 5320 F and 2100 psia. Three of the four primary coolant pumps were in operation and preparations underway to bring the reactor critical for operator training.
At 1335 on september 8, 1971, a technician de-energized the breakers to the reactor protective system to install a minor modification. This act de-energized the feed to the electromatic re-lief valve pilot valve solenoids allowing the valves to open.
' ale primary system pressure decreased to a low point of approximately 1280 psia over a period of 2 - 3 minutes until the blowdown was terminated by closure of the motor operated valves used to isolate the open relief valve.
The system pressure and temperature were back to normal in approximately one hour.
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I Wjar ibt /t (t u r, /hin- 9' /C 77 8306170012 740121 --
PDR ADOCK 05000255 -
S PDR COPY SENT REGIONg 7 ll 'J
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. .Dr. Peter A. Morris 2 US Atomic Energy Conmission September 16, 1971 The rate of depressurization of the reactor vessel and the pressurizer approximated the design rate for a pressurizer safety valve operation. The number of occurrences allowed for in the design was 200. Therefore, we conclude that-the integrity of the primary coolant system has not been compromised by this incident.
dEQUENCE OF EVENTS 1335 Breaker #13 on Panels HO and Y30 de-energized to allow for a minor modification to the reactor protective system. Refer to attached drawing E 8 Relays K1 and K3 which feed the electrically operated pressurizer relief valve bi-stables (RVlO42B and RV1043B) de-energized.
1335 ,RV1043B opened and released steam to the quench tank starting a decrease of primary system pressure. RV1042B had previ-
'ously been isolated by means of the motor operated isolation valve and did not pass steam during the incident. Refer to attached drawing M-201.
1336 Safety injection signal (SIS) actuated on both channels, however the A channel was blocked by action of the operator upon realization of the cause of the pressure drop. Safety injection pumps started.
1336 operater started MOV1043A closing.
1337 Charging pump P550 manually started.
1337 System pressure decay turned around at a low point of 1280 psia as MOV1043A closed stopping flow of steam to the quench
. , tank via HV1043B.
1338 Stopped safety injection pumps.
1343 Breaker #13 on panels nO and Y30 closed and power restored to relief valve control circuits.
l 1344 Returned charging and letdown to normal.
l 1400 As the system pressure recovered to a point above 1700 psia, the operator reset the safety injection channel B and returned
.. all equipment to normal.
1430 Primary coolant system pressure and temperature back to normal.
The coolant temperature and pressurize level swings of 3o F
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. , .Dr. Peter A. Morris 3 U3 Atomic Energy Commission September 16, 1971 and 4 percent respect!vely are considered insignificant.
CAUSE OF INCIDENT The basic cause of this incident was the non-standard desig-nation of contacts (as used by the architect engineer on the drawing) in the control circuit to the power operated relief valves. The technician was misled by the 'a' contact designation as shown on the drawing when in fact the circuit is wired using 'b' contact (s).
This led him to believe the relief valves would not open when the power was removed by opening breaker #13 on the panels Y10 and Y30.
CORRECTIVE ACTION PTANNED The drawing (s) will be corrected to indicate the "as built" condition using standard notations.
"A review of the control scheme design will be conducted by Consumers and the Reactor Supplier personnel to determine if any changes are desirable in order to lessen the probability of a second incident.
The plant operators will be furnished with revised procedures indicating steps to be utilized to minimize the blowdown if it should occur in the future.
Yours very truly, k, L Het.eter LMH/ERC/mho Robert L. Haueter Electric Production Superintendent - Nuclear CC: BHGrier USAEC Compliance, 000 L:_
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