ML14184A690
| ML14184A690 | |
| Person / Time | |
|---|---|
| Site: | Robinson, Brunswick  |
| Issue date: | 07/29/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8008260177 | |
| Download: ML14184A690 (6) | |
Text
'E UNITED STATES 0
NUOEAR REGULATORY COMMISSION REGION II on 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 In Reply Refer To:
JUL RII:JPO 50-325 Carolina Power and Light Company ATTN:
J. A. Jones Senior Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, NC 27602 Gentlemen:
Enclosed is IE Supplement No. 1 to IE Information Notice No. 80-06 "Notifi cation of Significant Events," which provides clarification on types of events that are required to be reported in accordance with 10 CFR-50.72, "Notification of Significant Events."
Sincerely, ames P. O'Reilly rector
Enclosures:
- 1.
IE Information Notice No. 80-06 Supplement No. 1 w/encl
- 2.
List of Recently Issued IE Information Notices cc w/encls:
A. C. Tollison, Jr., Plant Manager R. B. Starkey, Jr., Plant Manager 8 008Ro 17
UNITED STATES SSINS No.: 6870 NUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSPECTION AND ENFORCEMENT 8006190035 WASHINGTON, D.C. 20555 July 29, 1980 IE Information Notice No. 80-06 Supplement No. 1 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 § 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 § 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 deter'mine 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. 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 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 § 50.72(a).
IE Information Notice No. 80-06 July 29, 1980 Supplement No. 1 Page 2 of 2 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 fr6m and are part of the planned sequence during surveillance testing does not constitute an 'event reportable under this item.
Item (9) of § 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 1 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 BWR air ejector monitor (greater than 500,000 pel/sec; corresponding to 16 isotopes decayed to 30 minutes; or an increase of 100,000 pci/sec 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., 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, seiche
- c. Any tornado near site
- d. 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 flamable gas release
- e. Turbine failure
- 15. Other plant conditions exist that warrant increased awareness on the part of State and/or local offsite authorities or require plant shutdown under technical specification requirements or involve other than normal controlled shutdown (e.g., cooldown rate exceeding technical specification limits, pipe cracking found during operation)
- 16. Transportation of contaminated injured individual from site to offsite hospital
- 17. Rapid depressurization of PWR secondary side.
1-5
IE Information Notice No. 80-06 Enclosure Supplement No. 1 July 29, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 80-06 Notification of Signifi-7/29/80 All power reactor facilities Supplement 1 cant Events at Operating with an OL and near term Power Reactor Facilities OL applicants 80-28 Prompt Reporting Of 6/13/80 All applicants for and Required Information holders of nuclear power To NRC reactor construction 80-27 Degradation of Reactor 6/11/80 All Pressurized Water Coolant Pump Studs Reactor Facilities holding power reactor OLs or CPs 80-26 Evaluation of Contractor 6/10/80 All Part 50 Licensees QA Programs 80-25 Transportation of 5/30/80 Material Licensee in Pyrophoric Uranium Priority/Categories II-A, II-D, III-I and IV-DI; Agreement State Licensees in equivalent categories 80-24 Low Level Radioactive 5/30/80 All NRC and Agreement Waste Burial Criteria State Licensees 80-23 Loss of Suction to 5/29/80 All power reactor to Emergency Feedwater facilities with an Pumps OL or CP 80-22 Breakdown In Contamination 5/28/80 All power reactor Control Programs OLs and near term CPs 80-21 Anchorage and Support of 5/16/80 All power reactor Safety-Related Electrical facilities with an Equipment OL or CP 80-20 Loss of Decay Heat Removal 5/8/80 All light water reactor Capability at Davis-Besse facilities holding Unit 1 While in a Refueling power reactor OLs or CPs Mode