ML19338C384
| ML19338C384 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/29/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 8008150327 | |
| Download: ML19338C384 (1) | |
Text
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{lQ UNITED STATES 8"
i NUCLEAR REGULATORY COMMISSION 9
E REGION 111 3
e'['
799 ROOSEVELT ROAD g
'g GLEN ELLYN. ILLINOIS 60137 ANil 2 9 e)
Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 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, James G. Kep er Director l
Enclosures:
l 1.
Supplement' to IE Information l
Notice No. 80-06 2.
List of Recently Issued IE Information Notices cc w/ encl:
Mr. G. A. Reed, Plant NSIC Manager TIC Central Files Sandra A. Bast, Lakeshore Director, NRR/DPM Citizens for Safe Energy l
Director, NRR/ DOR Mr. John J. Duffy, Chief C. M. Trammell, ORB /NRR Boiler Inspector, Department PDR of Industry, Labor and Human Local PDR Relations 800815032.}
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UNITED STATES SSINS No.: 6870 1
NUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSPECTION AND ENFORCEMENT 8006190035 WASHINGTON, D.C.
20555 July 29, 1980 Supplement to IE Information Notice No. 80-06 NOTIFICATION OF SIGNIFICANT EVENTS AT OPERATING POWER REACTOR FACILITIES
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Description of Circumstances:
IE Information Notice No. 80-06 (IN 80-06) issued on February 27, 1980, forwarded a Federd Register Notice which indicated that the NRC regulations were amended by adding a new S 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 repo'rted 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 6 50.72 also suggest the-need for clarification and more definitive guidance. The general categorizas 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 S 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 S 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 natifications of cer'tain 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 S 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 Plar,ts").
It is recognized that some overlap and duplication exists between the reporting requirements of item (1) and other items of 6 50.72(a).
Supplement to IE Information Notice No. 80-06 July 29, 1980 4
Page 2 of 2 Item (7) of S 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 evept reportable under this item.
Item (9) of S 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
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to NUREG-0654 f
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I Supplemeat to IE Information Notice No. 80-06 Enclosure July 29, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued
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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 *IIJA, 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
EXAftFLE I'ifTIATillG _CONDIT. IONS: NOTIFICATION OF UNUSUAL EVENT J
1.
ECCS int tiated 2.
Radiological effluent technical, specification limits exceeded 3.
Fuel demage indication.. Examples:
High offges at SWR air ejector moniter (greater than 500.000 pei/ sect e.
correspoading to 16 isotopes. c'ecayed to 30 r,inutes; or an increase of 100.000 pct / hec within a 30 minute tima period) b.
High coolant activity sample. (e.g..,txcceding coolant technical speci.
fications for lodine spike)*'
Failed fuel ricnitor (PWR) indicates increase greater than 0.1% equiva)ent c.
fuel failures within 30 minutes..
4.
Abnnrmal coolant temperature and/or pressure or abnomal fual temperatures 5.
Exceeding either primary / secondary leak rate technical specificatten or prinary system leak rate technical,specificntion 6.
Failure of a safety or relief valve to close 7.
Loss of offsite pcwar or loss of onsite' AC power capability 8.
Loss of contsinment integrity requiring shutdown by technical specifications 9.
Loss of engineered safety featura:or fire protection system function requirir.g shutdown by technical specifications (e.g., because of malfunction, persen::e1 error or procedural. inadequacy)
- 10. Fire lasting more than 10 minutes:
- 11. Indica [ ions or alarms on process or effluent parameters not functional in centrol room to an extent requiring plant shutdown or cther significant loss of assesse.ent or comunication capability (e.g., plant computer, all meteorological instrumentation) -
- 12. Security threat or attempted antry or attempted sabotage
- 13. ftatural phenomenon being experienced or projected beyond usual levels a.
Any earthquake 6.
50 year ficoo or low water; tsunami., hurricane surge, seiche c.
Any tornado near site d.
Any hurricene 1-4
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- 14. Other I.azards b2ing experienced or projected Aircraft crash on-sitt or unusual aircraft. activity over facility a.
b.
Train derailrent on-site.
c.
Naar or onsite explosien d.
Near er onsite toxic or flammabie' gas release.
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e.
Turbine failure
- 15. Other plant conditions exist that warrant increiscJ awareness on the part of State and/or local nffsite authorities or require plant shutdown under technical specification requiramants or involveinther than naimal controlled shutdown (e.g., cooldown rate exceeding technical speci.fication limits, pipe cracking found'during operation)
- 16. Transportation of contaninsted injurad individual from site to offsite hospital
- 17. Rapid depressurization of 'WR secondary side.
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