ML18082A832
| ML18082A832 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/29/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8008070425 | |
| Download: ML18082A832 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 50-311 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
. July 29, 1980 The enclosed Supplement to IE Information.Notice ~o. 80-06 provides additional information with regard to an amendment to the Nuclear Regulatory Commission regulations requiring the immediate reporting by telephone of significant events at operating nuclear power plants. No written response is required.
Should you have any questions regarding this information notice, please contact this office.
Sincerely,
'-./.rvVVf f..-r/_ Wl. Clet~
Enclosures:
- 1.
Supplement to IE Information Notice No. 80-06 with Enclosure
- 2.
List of Recently Issued IE Information Notices CONTACT:
D. L. Caphton (215-337-5266).
cc w/encls:
F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station 8008070 "If 5.
A -
.e.
ENCLOSURE 1 UNlTED STATES SSINS No.: 6870
- .NUCLEAR REGULATORY COMMISSION 1
.. Ac:c:essi ans No.:
OFFICE OF INSPECTION AND ENFORCEMENT 8006190035 WASHINGTON, D.C.
20555 July 29, 1980 IE Information Notice No. 80-06
. Supp 1 ement Page 1 of 2 NOTIFICATION OF SIGNIFICANT EVENTS AT OPERATING POWER REACTOR FACILITIES Description OT c*ircumstances:
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 11, 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 ih accordance with§ 50.72 also suggest the need for clarification an~ 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 11serious events that could result in an impact on the public health and *safety.
11 The notification requirements in § 50.72 are* currently being evaluated to determine actions needed in light of pub 1 i c comments 011 and experi,ence 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 thresho1ds for notifications of {:ertain 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 9f 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 uNotification 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, 11Draft 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").
IE Information Notice No. 80-06 Supplement July 29, 1980 Page 2 of 2 It is recognized that some overlap and duplication exists between the. reporting requirements of item.Cl) and other items of§ 50.72(a).
Item (7) of § 50. l2(a) *requires notificat.ion of:
"Any event resulting in manual or automatic actuation of Engineered Safety Features, including Reactor Protection System.
11 Actuation of Engineered-Safety Features_ including the Reactor Protection System which re*sult from 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) requ.ires notification of:
11Any fatality or serious.
injury occurring on the. site and requiring transport to an offsite medical facility for treatment.
11 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 ti.me (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
l.
Enclosure to IE Information Notice No. 80-06 Supplement EXAMPLE INT-TING CONDITIONS:
NOTIFICATION -
UNUSUAL EVENT ECCS initiated 2.- Radiological effluent technical specification limits exceeded
- 3.
Fuel damage indication. Examples:
- a. High offgas at BWR air ejector monitor (greater than soo*,ooo µci/sec; corresponding to 16 isotopes decayed to 30 minutes; or an increase of 100,000 ~ci/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 techni~al 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 colTlllunication 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
Enclosure to IE Information Notice No. 80-06 Supplement e
- 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 flarmiable gas release
- e. iurbine failure
- 15. Other plant conditions exist that warrant increased awareness on the part of State and/or local offsite authorities or require plaAt shutdown under technical specification re9~irements or involve other than normal controlled shutdown (e.g., cooldown rate exceeding technical specificatton limits, pipe cracking found during operation)
- 16. Transportation of contaminated injured individual from site to offsite hospital
- 17.
Rapid depressurization of PWR secondary si.de.
1-5
e IE Information Notice No. 80-06 Supplement July 29, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 80..,.28 Prompt Reporting Of 6/13/80 All applJcants for and Required Information holders of nuclear power To NRC reactor construction per-mi ts 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 Priori-ty/Categories II-A, Il-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