ML17095A359
| ML17095A359 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/29/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8008150437 | |
| Download: ML17095A359 (12) | |
Text
0 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 July 29, 1980 Docket Nos.
50-275, 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
iver. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
The enclosed Information Notice supplements Information Notice No. 80-06 "Notification of Significant Events,"
and provides clarification on types of events that are required to be reported in accordance with 10 CFR 50.72, "Notification of Significant Events."
Sincerely, R.
H. Engelken Director
Enclosures:
1.
Supplement to IE Information Notice No. 80-06 2.
List of Recently Issued IE Information Notices cc w/enclosures:
W.
- Raymond, PG&E E.
B. Langley, Jr.,
PG&E R.
- Ramsay, PG&E, Diablo Canyon 8 0080y90$ +7
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 SSINS No.: 6870 Accessions No.:
8006190035 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 Register Notice which indicated that the NRC regulations were amended by adding a
new g 50.72, "Notification of significant events",
to 10 CFR Part 50.
The effective date of the new rule was February 29, 1980.
This Information Notice supplements IN 80-06 and provides 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 need to establish more defini-tive thresholds for notifications of certain types of events.
Experience so far with notifications being made in accordance with 9 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 g 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 g 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 5 50.72(a) requires notification of: "Any event requiring initiation of the licensee's emergency plan or any section of that plan."
Notifications unde~ 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. examples 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 HUREG-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 !E Information Notice No. 80-06 July 29, 1980 Page 2 of 2 Item (7) of 5 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 5 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 hospital 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 Appendix I to NUREG-0654
0
Supplement to IE Information Notice No. 80-06 Encl osure July 29, 1980 Information Notice No.
Subject RECENTLY ISSUED IE INFORMATION NOTICES Date Issued Issued To 80-28 80-27 80-26 80-25 80-24 80-23 80-22 80-21 80-20 Prompt Reporting Of Required Information To NRC Degradation of Reactor Coolant Pump Studs Evaluation of Contractor gA Programs Transportation of Pyrophoric Uranium Low Level Radioactive Waste Burial Criteria Loss of Suction to to Emergency Feedwater Pumps Breakdown In Contamination Control Programs Anchorage and Support of Safety-Related Electrical Equipment Loss of Decay Heat Removal Capability at Davis-Besse Unit I While in a Refueling Mode 6/13/80 6/11/80 6/10/80 5/30/80 5/30/80 5/29/80 5/28/80 5/16/80 5/8/80 All applicants for and holders of nuclear power reactor construction All Pressurized Water Reactor Facilities holding power reactor OLs or CPs 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 OL or CP All power reactor OLs and near term CPs All power reactor facilities with an OL or CP All light water reactor facilities holding power reactor OLs or CPs
e EXAMPLE INITIATING CONOITIONS:
NOTIFICATION OF UNUSUAL EVENT
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ECCS initiated 2.
Radiological effluent technical specification limits exceeded 3.
Fuel damage indication.
Examples:
a.
High offgas at 8MR air ejector monitor (greater than 500,000 pcf/sec; corresponding to 16 isotopes decayed to 30 minutes; or an ircrease of 100,000 pcf/sec with',n a 30 minute time period) b.
High coolant activity sample (e.g.,
exceeding coolant technical speci-fications for iodine spike)
Failed fuel monitor (PMR) 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 affsi te power or loss of onsite AC power capability 8.
Loss of containment integrity requiring shutdown by technical specifications 9.
Loss af engineered safety feature or fire protection system function requiring shutdown by technicat specfffcatfons (e.g.,
because of malfunction, personnel error or procedural inadequacy) 10.
Fire lasting more than 10 minutes T
ll.
Indications or alarms on process or effluent parameters not functional in
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control roam to an extent requiring plant shutdown ar other sfgnificant loss of assessment or communication capability (e.g., plant computer, all meteoralogfcal 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, seiche c.
Any tornado near si'te Any hurricane
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14, Other hazards being experienced or projected a.
Aircraft crash on-site or unusual aircraft activity over facflft b.
Train deraf leant on-site c.
Hear or onsite explosion d.
Hear or onsite toxic or flamnable gas release e.
Turbine failure 15.
Other plant conditions exist that warrant increased awareness n th of S ate and/or local offsite authorities or require plant shutdown under technical speci<ication requirements or invol ve other than normal controlled shutdown (e.gcooldown rate exceeding Xechnfcal speciffcation limits, pipe cracking found dur ing operation) 16.
Transportation of contaminated fnjured individual fmn site to offsite hospital 17.
Rapid depressurizatfon of l%R secondary side.
v 1-5