Bulletin 79-06A (Revision No. 1), Review of Operational Errors And System Misalignments Identified During The Three Mile Island Incident
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 April 18, 1979 IE Bulletin No. 79-06A (Revision No. 1) REVIEW OF OPERATIONAL ERRORS AND SYSTEM MISALIGNMENTS IDENTIFIED DURING THE THREE MILE ISLAND INCIDENT IE Bulletin 79-06A identified actions to be taken by the licensees of all pressurized water reactors designed by Westinghouse. Item No. 3 of the actions to be taken, as stated in the original bulletin, was: "3. For your facilities that use pressurizer water level coincident with pressurizer pressure for automatic initiation of safety injection into the reactor coolant system, trip the low pressurizer level setpoint bistables such that, when the pressurizer pressure reaches the low setpoint, safety injection would be initiated regardless of the pressurizer level. In addition, instruct operators to manually initiate safety injection when the pressurizer pressure indication reaches the actuation setpoint whether or not the level indication has dropped to the actuation setpoint." Information from licensees and Westinghouse has identified that implementation of this action would preclude the performance of surveillance testing of the pressurizer pressure bistables without initiating a safety injection. In order to permit surveillance testing of the pressurizer pressure bistables, the low pressurizer level bistables that must operate in coincidence with the low pressurizer pressure bistables may be restored to normal operation for the duration of the surveillance test of that coincident pressurizer pressure channel. At the conclusion of the surveillance test of each pressurizer pressure channel, the coincident pressurizer level channel must be returned to the tripped mode defined in Action Item 3 of IE Bulletin 79-06A. As a result, Item 3 should be revised as follows: . IE Bulletin No. 79-06A April 18, 1979 (Revision No. 1) Page 2 of 2 "3. For your facilities that use pressurizer water level coincident with pressurizer pressure for automatic initiation of safety injection into the reactor coolant system, trip the low pressurizer level setpoint bistables such that, when the pressurizer pressure reaches the low setpoint, safety injection would be initiated regardless of the pressurizer level. The pressurizer level bistables may be returned to their normal operating positions during the pressurizer pressure channel functional surveillance tests. In addition, instruct operators to manually initiate safety injection when the pressurizer pressure indication reaches the actuation setpoint whether or not the level indication has dropped to the actuation setpoint." Item 13 of the actions to be taken, as stated in the original bulletin, was: "13. Propose changes, as required, to those technical specifications which must be modified as a result of your implementing the above items." Long term resolutions of some of these required actions may require design changes. Therefore, Item 13 of actions to be taken should be revised as follows: "13. Propose changes, as required, to those technical specifications which must be modified as a result of your implementing the above items and identify design changes necessary in order to effect long term resolutions of these items." For all light water reactor facilities designed by Westinghouse with an operating license, respond to Items 1-12 within 10 days of the receipt of this Bulletin. Respond to Item 13 (Technical Specification Change proposals and identification of design changes in 30 days.) The other requirements of IE Bulletin 79-06A remain in effect. Approved by GAO, B180225 (R0072); clearance expires 7-31-80. Approval was given under a blanket clearance specifically for identified generic problems.
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021