ML19338C385

Forwards Supplemental IE Info Notice 80-06, Notification of Significant Events at Operating Power Reactor Facilities. No Written Response Required

ML19338C385
Person / Time
Site:	Davis Besse
Issue date:	07/29/1980
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Crouse R TOLEDO EDISON CO.
References
NUDOCS 8008150329
Download: ML19338C385 (1)

Text

/

4 UNITED STATES 8~

~1 NUCLEAR REGULATORY COMMISSION E

. E REGION lli e

799 ROOSEVELT ROAD e*

GLEN ELLYN. ILLINOIS 60137

@L 2 9

• Docket No. 50-346 Toledo Edison Company ATTN:

Mr. Richard P. Crouse Vice President Energy Supply Edison Plaza 300 Madison Avenue Toledo, OH 43652 Gentlemen:

The enclosed Information Notice supplements Information Notice No. 80-06 " Notification of Signiiicant 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,

~

0 James G. Kepp r Director

Enclosures:

1.

Supplement to IE Information Notice No. 80-06 2.

List of Recently Issued IE Information Notices cc w/ encl:

Mr. T. Murray, Station NSIC Superintendent TIC Central Files Harold W. Kohn, Power Director, NRR/DPM Siting Commission Director, NRR/ DOR Helen W. Evans, State PDR of Ohio Local PDR 8 0 08150 3M Q

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UNITED STATES SSINS No.: 6870 NUC'_ EAR REGULATORY COMMISSION Accessions No.:

0FFICE 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 KACTOR 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 S 50.72, " Notification of significant events", to 10 CFR Part 50.

The effective date of the new rcle was February 29, 1980.

This Information Notice supplements IN 80-06_an1 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 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 6 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 actior.s 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 6 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 olant.

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 Radiclogical 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 9 50.72(a).

Supplement to IE Information Notice No. 80-06 July 29, 1980 i

Page 2 of 2 Item (7) of 6 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 9 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 observatior, 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

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Supplement to IE Information Notice No. 80-06 Enclosure 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 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-Dy 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

[,

EXNtFLE I:ifTIATING_,CO?IDITIONS: PIOTIFICATION OF UNUSUAL EVENT 4

1.

ECCS 'ini tiated 2.

Radiological efnuent technical. specification limits exceeded 3.

Fuel damage indication.. Examoles:

High offgas at BWR air ejector moniter (greater than 500,000 pei/sec;

e..

correspoading to 16 isotopes. decayed to 30 minutes; or an increase of 100,000 pct / hee within a 30 minute tima period) b.

High coolant activity sample.(e.g.,4xcceding coolant technical speci-fications for iodine spike)*'

Failed fuel nonitor'(PWR) indicates increase greater than 0.1% equiva)ent c.

fuel failures within 30 minutes..

4 Abnormal coolant temperature and/or pressure or abnomal fual temperatures 5.

Exceeding either primary / secondary leak rate technical specificaticn or prinary system leak rate tec.hnical, specification 6.

Failure of a safety or relief valve to close 7.

t.oss of offsite pcwar or loss of onsite' AC power capability 8.

Loss of cantsinment integrity requiring shutdown 'oy technical sr.ecifications 9.

Loss of engineered safety feature:or fire protection system function requirir.g shutdown by technical specifications (e.g., because of malfunction, perscnael errer 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 assessment or comunication capability (e.g., plant computer, all meteorological instrumentation)

12. Security threat or attempted antry or attempted sabotage

13. fiatural phenomenon being experienced or projected beyond usual levels I

a.

Ar.y earthquake b.

50 year flood or low water; tsunami, hurricant; surge. seiche l

c.

Any tornado near site d.

Any hurricens l-4

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e it. Other I,azards b2ing exnerienend or ?rojected Aircraft crash on-sit 2 or unusual aircraft. activity over facility a.

b.

Train derailment on-site c.

N?ar or onsite explosien-d.

Near er onsite toxic or flammable' gas. release e.

Turbine failure 15.

Other plant conditions exist that warrant increased aw.ireness on the part of Stata and/or local offsite authoritiestor require plant shutdown under technical specification requiraments or involveinther than normal controlled shutdown (e.g., cooldown rate exceeding technical specification limits, pipe cracking found during operation) 16.

Transportation of contaminsted injured individual from site to offsite hospital

'7.

Rapid depressurization of PRR secondsry side.

4 9

9 0

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