Information Notice 1980-06, Notification of Significant Events at Operating Power Reactor Facilities
| ML031180150 | |
| Person / Time | |
|---|---|
| Site: | 05000000 |
| Issue date: | 07/29/1980 |
| From: | NRC/OI |
| To: | |
| References | |
| IN-80-006, NUDOCS 8006190035 | |
| Download: ML031180150 (5) | |
UNITED STATES
SSINS No.: 6870
NIUCLEAR REGULATORY COMMISSION
Accessions No.:
OFFICE OF INSPECTION AND ENFORCEMENT
8006190035 WIASHINlGTON, D.C.
20555
July 29, 1980
Supplement IE Information
Notice No. 80-06 NOTIFICATION OF SIGNIFICANT EVENTS AT OPERATING POWER REACTOR FACILITIES
Description of Circumstances
IE Information Notice No. 80-06 (IN 80-06) issued on February 27, 1980,
forwarded a Federal Resister Notice which indicated that the NRC regulations
were amended by adding a new i 50.72, "Notification of significant events", to
The effective date of the new rule was February 29, 1980.
This Information Notice supplements IN 80-06 and orovides clarification on
types of events that are required to be reported in accordance with the rule.
Public comments on the rule indicate the need for more detailed clarification
on what occurrences are reportable in regard to certain event types listed in
the rule.
Commenters particularly stressed the neec
3o establish more defini- tive thresholds for notifications of certain types of events.
Experience so
far with notifications being made in accordance with § 50.72 also suggest the
need for clarification and more definitive guidance.
The general categoriza- tion of some of the event types listed in the rule has resulted in notifica- tions of events of less significance than was originally intended.
As stated
in the Federal Register Notice implementing § 50.72, the rule was intended to
require immediate notification of "serious events that could result in an
impact on the public health and safety."
The notification requirements in § 50.72 are currently being evaluated to
determine actions needed in light of public comments on and experience with
the rule.
Notwithstanding future actions which may include some modifications
to the rule and supplementary regulatory guidance, a short term need exists
for clarifying the thresholds for notifications of certain categories of
events. The following paragraphs provide clarification on what is reportable
pursuant to the event categories listed in items (1), (7) and (9) of the rule.
Item (1) of § 50.72(a) requires notification of: "Any event requiring
initiation of the licensee's emergency plan or any section of that plan."
Notifications under this item refer to those initiating events or conditions
that place the facility in a "Notification of Unusual Event" status. An
unusual event indicates a potential degradation of the level of safety of the
plant.' 4xamples of initiating events or conditions that would be categorized
as an unusual event are listed on the enclosed pages 4 and 5 of NUREG-0610,
"Draft Emergency Action Level Guidelines for Nuclear Power Plants" (Appendix 1 to NUREG-0654, "Criteria for Preparation and Evaluation of Radiological
Emergency Response Plans and Preparedness in Support of Nuclear Power Plants").
It is recognized that some overlap and duplication exists between the reporting
requirements of item (1) and other items of g 50.72(a).
Supplement to IE Information
July 29, 1980
Notice No. 30-06 Item (7) of § 50.72(a) requires notification of:
"Any event resulting in
manual or automatic actuation of Engineered Safety Features, including Reactor
Protection System." Actuation of Engineered Safety Features including the
Reactor Protection System which result from and are part of the planned sequence
during surveillance testing does not constitute an event reportable under this
item.
Item (9) of I 50.72(a) requires notification of:
"Any fatality or serious
injury occurring on the site and requiring transport to an offsite medical
facility for treatment." Serious injury is considered to be any injury that
in the judgment of the licensee representative will require admission of the
injured individual to a hosoital for treatment or observation for an extended
period of time (greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />).
Injuries that only require treatment
and/or medical observation at a hospital or offsite medical facility, but do
not meet the conditions specified above, are not required to be reported.
Enclosure:
Pages 4 and 5 of ADpendix I
to NUREG-0654
EXAMPLE INITIATING CONDITIONS: NOTIFICATION OF UNUSUAL EVENT
1. ECCS initiated
2. Radiological effluent technical specification limits exceeded
3. Fuel damage indication.
Examples:
a. High offgas at SWR air ejector monitor (greater than 500,000 yci/sec;
corresponding to 16 Isotopes decayed to 30 minutes; or an Increase of
100,000
jcilsec within a 30 minute time period)
b. High coolant activity sample (e.g.. exceeding coolant technical speci- fications for iodine spike)'
c. Failed fuel monitor (PWR) indicates increase greater than 0.1% equivalent
fuel failures within 30 minutes.
4.
Abnormal coolant temperature and/or pressure or abnormal fuel temperatures
5. Exceeding either primary/secondary leak rate technical specification or
primary system leak rate technical specification
6. Failure of a safety-or relief valve to close
7.
Loss of offsite power or loss of onsite AC power capability
8. Loss of containment integrity requiring shutdown by technical specifications
9. Loss of engineered safety feature or fire protection system function
requiring shutdown by technical specifications (e.g., because of malfunction, personnel error or procedural inadequacy)
10.
Fire lasting more than 10 minutes
11.
Indications or alarms on process or effluent parameters not functional in
control room to an extent requiring plant shutdown or other significant
loss of assessment or communication capability (e.g.s plant computer, all
meteorological instrumentation)
12.
Security threat or attempted entry or attempted sabotage
13.
Natural phenomenon being experienced or projected beyond usual levels
a. Any earthquake
b.
50 year flood or low water, tsunami, hurricane surge, selche
c.
Any tornado near site
'J.
Any hurricane
1-4
14.
Other hazards being experienced or projected
a. Aircraft crash on-site or unusual aircraft activity over facility
b. Train derailment on-site
c. Near or onsite explosion
d. Near or onsite toxic or ftamaable gas release
e. Turbine failure
15.
Other plant conditions exist that warrant increased awareness on the part
of State and/or local offsite authoritles or require plant shutdown under
technical specification requirements or involve other than normal controlled
shutdown (e.g., cooldown rate exceeding technical Peccirication limtts, pipe
cracking found during operation)
16.
Transportation of contaminated injured individual from site to offsite
hospital
17.
Rapid depressurization of PWR secondary side.
.
, V
1-5
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Notice xo.
0-'6 enclosure
July 29,
1980
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Subject
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80-28
30-27
30-25
30-23
80-24
Prompt Reporting Of
Required Information
To N'RC
Degradation of Reactor
Coolant %umo Studs
.
Evaluation of Contractor
OA Programs
Transcortation of
Pyrophoric Uranium
Low Level Radioactive
Wiaste Burial Criteria
Loss of Suction to
to Emergency Feedwater
Pumps
Breakdown In Contamination
Control Programs
Anchorage and Support of
Safeity-Related Electrical
Equipment
Loss of Decay Heat Removal
Capability at Davis-Besse
Unit 1 While in a Refueling
Mode
6/13/30
6/11/80
5/10'/80
5/30/80
5/30/80
5/29/80
5/28/80
5/16/80
5/8/80
Issued To
All applicants for and
holders of nuclear power
reactor construction
All Pressurized Water
Reactor Facilities
holding power reactor
All Part 50 Licensees
Material Licensee in
Priority/Categories II-A,
II-D, III-I and IV-DI;
Agreement State Licensees
in equivalent categories
All NRC and Agreement
State Licensees
All power reactor
facilities with an
All power reactor
All power reactor
facilities with an
All light water reactor
facilities holding
80-23
80-22
80-21
80-20