ML19347C474
| ML19347C474 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/27/1972 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19347C471 | List: |
| References | |
| NUDOCS 8011190567 | |
| Download: ML19347C474 (11) | |
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5.3 ACTION TO BE TAKEN IN THE EVENT OF AN ABNORMAL OCCURRENCE IN PLANT OPERATION Applies to administrative action to be followed 'in the event of an abnormal occurrence in Plant operation. An abnormal occurrence is defined as:
1.
Violations of Limiting Safety System Settings.
2.
Violations of Limiting Conditions for Operation.
3.
Engineered safety system component malfunctions or other component or system malfunctions which could, or threaten to, render the system incapable of performing its intended safety function.
4.
Abnormal dyradation of one of the several boundaries which are designed to contain the radioactive materials resulting from the fission process.
5.
Uncontrolled or unanticipated changes in reactivity greater than 1% 6/rs.
6.
Observed inadequacies in the implementation of either administrative or procedural controls, such that the inadequacy could have caused the existence or development of an unsafe condition in connection with the operation of the reactor.
7.
Uncontrolled or unplanned release of radioactive material from the site in excess of 1/10 of 1% of trie Timits established in these Technical Specifications.
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Any abnormal occurrence (as defined above) shall be reported to the Manager of Operations and shall be reviewed by the Plant Operations Review Committee.
This Committee shall prepare a separate, sequentially numbered, report fo'r'each abnormal Each report shall describe the circumstances leading occurrence.
up to and resulting from the occurrence, the corrective action taken by the shift, and an attempt to define the cause of the occurrence; appropriate action shall be recommended to prevent or reduce the probability of a repetition of the occurrence.
Copies of all such reports shall be submitted to the Chairman of the Nuclear Safety Audit and Review Committee for review and to the Manager of Operations for review and approval of any recommendations. All abnormal occurrences shall be reported in the Monthly Plant Operations Report.
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5.7 PLAriT REPORTING REQUIREMENTS In addition to reports required by applicable regulations, Yankee Atomic Electric Company shall provide the following infonnation:
A.
Events requiring reports within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (by telephone and telegraph to Region I Compliance Office):
a.
Incidents or conditions relating to operation of the Plant
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which prevented or c.ould have prevented the performance of engineered safety features as described in these Specifications.
b.
Any significant variation of measured values from a corresponding predicted value of safety-connected operating parameters occurring during the initial' criticality of the core following refueling.
c.
Any abnormal occurrences as specified in the Definitions Section of these Specifications.
- d. ' Incidents or conditions which resulted in'a safety limit being exceeded as established in these Specifications.
B.
Events requiring reports with 10 days (in writing to the Director, Division of Reactor Licensing, U.S.A.E.C., Washington, D.C. 20545):
a.
In the event a redundant component (or system) is determined to be out of service for periods longer than_ those specified in other sections, it shall be the subject of a special report.
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O This repor't shall describe:
- 1) The nature of the problem and the specific steps to be taken to remedy the situation.
- 2) An estimate of the time required to return the component (or system) to an operable condition.
- 3) The amount of component (or system) redundancy remaining or the availability of other system (s) to perform the same function as the inoperable component (or system).
Surveillance requirements on the operable component (or 4) system).
b.
Any abnormal occurrences as specified in the Definitions Section of these Specifications.
c.
Incidents or conditions relating to operation of the Plant which prevented the performance of engineered safety features.
C.
Events requiring reports with 30 days (in writing to the Director, Division of Reactor Licensing, U.S.A.E.C., Washington, D.C. 20545):
Any substantial variance from performance specifications a.
contained in these Specifications or in the Final Safety l
a Analysis Report.
t b.
Any significant change in transient or accident analysis as described in the Final Safety Analysis Report.
- c. -Any changes in plant organization as described in 5.1.
d.
Observed inadequacies in the implementation of administrative or procedural controls.
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The written report, and to the extent possible, the preliminary telephone and telegraph report,'should describe, analyze and evaluate safety implications and outline the measures taken to assure that
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the cause of the condition is determined and to' indicate the corrective action, including any significant changes made to procedures and to the quality assurance program, taken to preclude repetition of the occurrence and of similar occurrences involving similar components or systems.
In addition, the written report should relate any failures or degraded performance of systems and components for this incident to similar equipment failures that may have occurred previously at the facility.
Tne evaluation of the safety implications.of the incident should consider the cumulative experience obtained from the record of previous failures and malfunctions of the affected systems and components or of similar equipment.
D.
Routine Operating Reports (in writing to the Director, Division of Reactor Licensing, US AEC, Washington, D.C. 20545):
A routine operating report shall be submitted monthly. The following information shall be provided:
1.
Nuclear a.
Number of hours the plant was operated.
b.
Number of times the reactor was made critical.
Gross thermal power generated (in MWH).
c.
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d.
Operating histogram, showing the thermal power level of the reactor verstrs time, for the report period, e.
Equivalent Full Power Hours.
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Electrical a.
Gross power generated (in MWH).
b.
Net power generated (in MWH).
Length of time generator was on line (in hours).
c.
3.
Shutdowns a.
Number of scrams and shutdowns.
b.
Duration of downtime (in hours),
c.
Reasons for outage.
- 4.. Maintenance a.
Nature of the maintenance; e.g.,-routine, emergency, preventive or_ corrective.
b.
The effect, if any, on the safe operation of the reactor.
c.
The cause of any malfunction for which' corrective maintenance
.was required, d.
The results of any such malfunctions.
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Corrective and preventive action taken to preclude l
recurrence.
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Time required for completion.
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5.
Radioactive Liquid Wasa a.
Total curie activity discharged.
l b.
Total curies of tritium discharged.
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c.
Total volume (in gallons) of liquid waste discharged.
d.
Total volume (in gallons) of dilution water used.
Average concentration (in uc/cc) a,t point of discharge.
e.
f.
Time and date of the maximum concentration released (for any consecutive ~24 hours during the reporting period).
g.
The MPC used and the basis for this MPC.
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6.
Gaseous Waste a.
Total curie activity discharged (in curies).
b.
Time and date of the maximum activity released (for any consecutive 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the reporting period),
c.
The MPC used, if greater than:
1.
3 x 10-8 uc/cc for noble and activation gas.
2.
1.43 x 10-13 uc/cc for iocines with >8 day half life.
7.
Solid Radioactive Waste a.
Total volume (in cubic feet) of solid' waste generated.
b.
Gross curie activity involved.
c.
Dates and disposition of the material, if shipped offsite.
E.
Special Reports Reports on the following areas shall be submitted as noted-Area Reference Submittal Date a.
Containment Leak Rate 4.4 60 days after completion Testing (1) of each integrated test b.
In-service Inspection 4.9 As per Section XI ASME Evaluation Boiler Codes
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(1) Each integrated leak rate shall be the subject of a summary technical report, which includes a schematic arrangement of the leakage measurement system, the pressure, temperature, and humidity instrumentation employed including their sensitivity, the test procedure, test results in graphical and tabular form and the analysis and interpretation of leakage rate results in meeting the allowable leakage rates specified in the license Summaries of local leak test results shall be included in the same report to permit evaluation of local leak testing as compared to integrated leak rate testing.
c.
A report shall be submitted to the Commission within 60 days after January 1 and July 1 of each year of operation specifying total quantities of radioactive material released to unrestricted areas in liquid and gaseous effluents during the p,evious six months and such other information on releases as may be required to estimate exposures to the public resulting from effluent releases.
If quantities of radioactive material released during the reporting period are unusual for normal reactor operations, including expected operational occurrences, the report shall cover this specifically.
This report shall also include a section on environmental monitoring as outlined below.
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O Environmental Monitoring a.
Descriptive matdrial covering the offsite environmental surveys performed during the reporting period including information on:
1.
The number and types of samples taken; e.g., air, river, bottom, surface water, soil, fish.
2.
The number and types of measurements made; e.g.,
dosimetry.
3.
Locations of the sample points and monitoring stations.
4.
The frequency of the surveys.
5.
A summary of survey results.
b.
If a particular sample or measurement indicates statistically significant levels of radioactivity above established or concurrent backgrounds, the following information shall be provided:
i 1.
The type of arialysis performed; e.g., alpha, beta, gamma and/or isotopic.
2.
The minimum sensitivity of the monitoring system.
3.
The measured radiation level or sample concentration.
4.
The specific times when samples were taken and measurements were made.
5.
An estimate of the likely resultant exposure to the public.
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o On the basis of such reports and any additional information the {ommission may obtain from the Licensee or others, the Commission may from time to time require the ' Licensee to t'ake such action as the Commission deems appropriate.
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DATE OF DOC:
DATE REC'D lLTR IGMO RP2 WHER Yankee Atomic Electric Cc=pany Westbercugh,!bss. 01581 L. E. Minnick 11-27-72 11-29-72 x
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DESCRIPTION:
vNCLOSURES:
Ltr re our 9-28-72 ltr, notarized 11-27-72, (1) Sec 5 3 - Action to be taken in the event requesting proposed change No. 105 to Tech of an Abnormal Occurrence in Plant Operatior Specs, & trans the followin6:
(2) Plant Reporting requirements to the present plant Tech Specs....Sec 5 7
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