ML19340E606
| ML19340E606 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/08/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-06-04, TASK-6-4, TASK-RR LSO5-80-12-005, LSO5-80-12-5, NUDOCS 8101150033 | |
| Download: ML19340E606 (5) | |
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y Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
RE: MILLSTONE SEP TOPIC VI-4, CONTAINMENT ISOLATION SYSTEM -
REQUEST FOR ADDITIONAL INFORMATION The enclosed request for additional information has been prepared as part of our evaluation of the bypassing and resetting of engineered safety features, including the containment isolation system, at Oyster Creek.
Response within 30 days is requested so that we maintain the present review schedule.
Sincerely, Dennis M. Crutchfield, C ief Operating Reactors Branch #5 Division of Licensing l
Enclosure:
As stated cc w/ enclosure:
See next page 810115 00'a3 g
Mr. W. G. Counsil MILESTONE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-245 cc William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Development Hartford, Connecticut 06103 Department of Planning and Energy Poliqy Natural Resources Defense Council 20 Grand Street 917 15th Street, N. W.
Hartford, Connecticut 06106 Washington, D. C.
20005 Director, Technical Assessment Division Northeast Nuclear Energy Company Office of Radiation Programs ATTN: Superintendent (AW-459)
Millstone Plant U. S. Environmental Protection l
P. O. Box 128 Agency Waterford, Connecticut 06385 Crystal Mall #2 Arlington, Virginia 20460 Mr. Janes R. Himmelwright Northeast Utilities Service Conpany U. S. Environmental Protection P. O. Box 270 Agency i
Hartford, Connecticut 06101 Region I Office ATTN: EIS COORDINATOR Resident Inspector JFK Federal Building c/o U. S. NRC Boston, Massachusetts 02203 P. O. Box Drawer KK Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 First Selectman of the Town of Waterford I
Hall of Records 200 Boston Post Road Waterford, Connecticut 06385 John F. Opeka Systens Superintendent Northeast Utilities Service Conpany P. O. Box 270 Hartford, Connecticut 06101 l
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MILLSTONE 1 REQUEST FOR ADDITIONAL INFORMATION BYPASS AND RESET OF CONTAINMENT ISOLATION AND OTHER ENGINEERED SAFETY FEATURES The following requirements are being used to evaluate the safety signals to all Engineered Safety Features (ESF) equipment which may have manual override capabilities:
Criterion 1--In keeping with the requirenents of General Design Criteria 55 and 56, the overriding of one type of safety-actuation signal (e.g.,
radiation) should not cause the blocking of any other type of safety-actuation signal (e.g., pressure) for those valves that have no function besides containment isolation.
Criterion 2--Sufficient physical features (e.g., key lock switches) are to be provided to facilitate adequate administrative controls.
Criterion 3--A system level annunciation of the overriden status should be provided for every safety system impacted when any override is active (see R.G. 1.47).
Criterion 4--Diverse signals should be provided to initiate isolation of the containment ventilation system.
Specifically, containment high radiation, safety injection actuation, and containment high pressure (where containment high pressure is not a portion of safety injection actuation) should automatically initiate containment ventilation isolation.
Criterion 5--The instrumentation and control systems provided to initiate the ESF should be designed and qualified as safety-grade equipment.
Criterion 6--The overriding or resetting of the ESF actuation signal should not cause any valve or damper to change position.
I The following definition is given for clarity of use:
a.
Override: The signal is still present, and it is blocked in order to perform a function contrary to the signal. The term, " override," where used in this Request for Infonnation, includes functionally equivalent techniques of signal modification (e.g., bypass).
a.
Reset: The signal has come and gone, and the circuit is being cleared in order to return it to normal condition.
s The information presented in your FSAR and your letters of January 2,1979, and April 27,1979, is not sufficient to determine if the above requirements are met for the safety signals to all Engineered Safety Features (ESF) equipment.
Therefore:
1.
Clarify the discrepancy between your January 2,1979 leter that indicates that either high dry well pressure or low reactor water level will actuate closure of the purge valves and Technical Specification basis 3.2 that indicates that hign radiation levels close the ventilation inlet and outlet valves.
2.
Identify, using diagrams and drawings as needed:
What isolation valves are involved in each line from the drywell to a.
the atmosphere.
3.
For each of these valves, identify all signals that initiate automatic or nasual closure of that valve.
c.
For each valve, indicate if any of the signals of 2.b above can be bypassed or overridden and describe the method used to establish each bypass.
3.
Should an override bypass more than one actuation signal, provide a comit-ment to change the design to conform to Criterion 1 above.
4.
The NRC requires that all override and reset switches have physical provisions to aid in the administrative control of the override or reset function. You have indicated that a keylocked switch is used for the 2" drywell vent valves.
Describe the physical provisions supplied with your other manual bypass control switches and reset switches. If no such provisions are presently provided, describe the modifications you are going to make to meet Criterion 2 above.
5.
The NRC requires that the override of a system actuation signal be annun-ciated at the system level. You have indicated that "any safety actuation signal which is bypassed at the system level will provide continuous indication in the control room." Describe the annunciation system that is used to satisfy Criterion 3 above.
6.
The NRC requires that, at a mininum, containment ventilation isolation (CIV) be accocplished on any of the following diverse conditions:
1.
Drywell pressure high 2.
Safety injection actuation 3.
Drywell radiation high.
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Describe how Millstone i satisfies this requirement.
I
s.
3-7.
The NRC requires signals that initiate containment isolation be derived from safety-grade (class IE) equipment. Describe the qualifications of the equipment used to meet Criterion 5 above.
8.
Verify that the overriding or resetting of a safety actuation signal does not cause any valve or dam 9er to change position. If this informa-tion was supplied as part of TMI Lessons Learned, please provide specific references.
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