ML18081B289
| ML18081B289 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/13/1980 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 8004020256 | |
| Download: ML18081B289 (4) | |
Text
Docket No. 50-311 NRC PDR Local PDR LWR #3 File -
E. L icitra A. Dromerick
- 0. Parr
.. M. Rushbrook Mr. R. L. Mittl, General Manager Lic~nsing and Environfuent-
- Engineering and Construction Department Public Service Electric -and Gas Company 80 Park Place
- Newark, New Jersey 07101
Dear Mr. Mittl:
S. Varga F. Wi 11 i a*ms OELD IE (3)
MAR 13 1980 BCC:
.1-\\CRS (16)
SUBJECT:
POTENTIAL DESIGN DEFICIENCIES IN BYPASS, OVERRIDE,. AND RESET CIRCUITS OF ENGINEERED SAFETY FEATURES Discussion Of Deficiencies Several instances have been reported where automatic closure _of. the containment ventilation/purge valves would not have occurred because the safety actuation
-signals were either manually overriden or bypassed (blocked) _during normal_
plant operations.
In addition, a related design deficiency with regard to the resetting of engineered safety feature aetuation signals has been found at several operating facilities where, upon the reset of an ESF signal, certain safety related equipment would return to its non-safety mode~
Specifically, on Ju*ne 25, 1978, Northeast Nuclea*r Energy Company discovered that intermittent containment purge operations had been conducted at Millstone Unit No. 2 with the safety actuation signals to redundant.containment purge isolation valves. (48 inch butterfly valves) manually overriden and inoperable. The isola-tion signals which are required to automatica11y close the purge valves to assure containment integrity were manually overriden to allow purging of containment with a high radiation signal present. The manual override circuitry designed by the plant's architect/engineer defeated not only the high radiation si gna 1 but also all other isolation signals to these valves. To manually override a safety actuation signal, the operator cycles the valve control-switch to the closed position and then to the open position. This action energized a relay which blocked the safety signal and allowed manual* operation independent of any safety actuation signal. This circuitry was designed to p:ermit reopening of certain valves after an accident to allow manual operation of required safety equipment.
OFFICE..,,-._ **..*...**.... -. - - -. - -.. -. -. - -...
SURNAME **.....*.... - -. - -.'. -...... -.. - -.. -. -.
DATE................ :
- _... *. _... *;... _... : _.
- YI/.)
t/
................................................... ~...................
-. -... -*.. --. -.. -..... _.. soo:.to. ~o. _
.Z.. S.6 __.. __.. _... _.... _:
- . NRC FORM 3_18 (9-76) NRCM 0240 1:ru.s_ GOVERNMENT PRINTING OFFICE: 1979-289-369
Mr. R. L. Mittl, General Man~ger r:
MAR 13 1980 On September 8, 1978, the staff was advised that, as a matter of routine, Salem Unit No. l had been venting the containment through the containment ventilation system valves to reduce pressure. In certain instances this venting has occurred with the containment high particulate radiation monitor isolation signal to the purge and pressure-vacuum relief valves overridden.
The override of this containment isolation signal was accomplished by re-setting the train A and B reset buttons. Under these circumstances, six valves in the containment vent and purge systems could be opened with the radiation isolation signal present. This override was performed after verifying that the actual containment particulate levels were acceptable for venting. The licensee, after further investigation of this practice,
- determined that the reset of the particulate radiation monitor alarm also overrides the containment isolation signal to the purge valves such that the purge valves would not have automatically closed on an emergency core cooling system (ECCS) safety injection signal.
A related design deficiency was discovered during a review of system operation following a recent unit trip and subsequent safety injection at North Anna No. 1.
Specifically, it was found that certain equipment important to safety (for example, control room habitability system dampers) would return to its non-safety mode following the reset of an ESF signal.
In addition, many utilities do not have safety grade radiation monitors to initiate containment isolation.
Safety Significance The overriding of certain containment ventilation isolation signals could also bypass other safety actuation signals and thus prevent valve closure when the other isolation signals are present. Although such designs may be acceptable, and even necessary, to accomplish certain reactor functions, they are generally unacceptable where they result in the unnecessary bypassing of safety actuation signals. Where such bypassing is also inadvertent, a more serious situation is created especially where there is no bypass indication system to alert the operator.
Where the resetting of ESF actuation signals, such as safety injection, directly causes equipment important to safety to return to its non-safety mode, protec-tive actions of the affected systems could be prematurely negated when the associated actuation signal is reset. Prompt operator action would be required*
to assure that the necessary equipment is returned to its emergency mode.
The use of a non-safety grade monitor to initiate containment isolation could seriously degrade the reliability of the isolation system.
Staff Posit ion It is our position that, in addition to other applicable criteriat the following should be satisified for all operating license applications currently under review:
OFFICE~,............*...* :............ ******
. ~URNAME ***.********..**....... :... * *........*............. *.*.* *.*................... ~..... :... *.,*.........................
DATE...
NR.C*FORM 318 (9-76) NRCM 0240
... -tru.s. GOVERNMENT PRINTING OFFICE: 1979-289-369
Mr. R. L. Mittl~ General Manager MAR 13 1980.
- 1)
The overridinga of one type of safety actuation signal (e.g., parti-culate radiation) should not cause the blocking of any other type of safety actuation signal (e.g., iodine radiation, reactor pressure) for those valves that have no function other than containment isolation.
- 2) Physical features (e.g., key lock s~1itches) should be provided to en-sure adequate administrative controls.
- 3)
A system level annunciation of the overridden status should be provided for every safety system impacted when any override is active.
(Seo Regulatory Guide 1.47).
- 4)
The following diverse signals should be provided to initiate isolation of the containment purge/ventilation system: containment high radiation, safety injection actuation, and containment high pressure (where con-tainment high pressure is not a portion of safety injection actuation).
- 5)
The instrumentation systems provided to initiate containment purge ventila..,..
tion isolation should b~ designed and qualified to Class lE criteria.
- 6)
The overriding or resettingb of the ESF actuation signal should not ca_use any equipment to change position.
Accordingly, you are requested to review your protection system design to deter-mine its degree of conformance to these criteria.
You should report the results of your review to us by April 15, 1980~ describing any departures from the*
crit~ria and the corrective actions to be implemented. Design departures for which no corrective ~ction js planned should be justified.
Please advise if you have any questions on this matter.
CC: See next page Sincerely, Qrl~>:c~.S'..gned b':t O*:. D. Parr Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management The following definitions are given for clarity.
a.override: The signal is still present, and it is blocked in order to perform a function contrary to the signal.
~eset:
The signal has come and gone, and the circuit is being cleared in order to return it to the normal condition.
'":::::~*MR~~~~M *
~r~~wM.
- L~~~~BC. * * *
- DATE~.-~~-\\!)/~-~-..... ?~.(~./~?-. --. -~~-~~-. !.~?.... -.. -.. *--*-. -* -* -* -* * * * -* * -* -* ---* -----* --* * * * -* -** *
- NRC FORM 318 (9-76) NRCM 0240 1:fu.S:GOVERNMENT PRINTING OFFICE: 1979-289-369.
.*.\\
Mr. R. L. Mittl, General Manager cc:
Richard Fryling, llr., Esq.
Assistant General Counsel Public Servic~ Electric & Gas Company
. 80 Park Pl ace Newark, New Jersey 07100 Mark Wetterhal111, Esq.
Conner, Moore & Caber 1747 Pennsylvania Avenue, N.W.
Suite 1050
- Washington, D.C.
20006 Mr. Leif J. Norrholm U. S. Nuclear Regulatory Conmission Region I Drawer I Hancocks Bridge, New Jersey 08038 MAR 1 3 1980